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EDITORIAL STAFF

/ 编辑团队

CONTENTS

Interviews

News

Nuclear Glossary

Highlights of the Month

Company News

NPP News

International Cooperation

Interview with Zhang Wenyin, Nuclear Power BU Manager, Bureau Veritas

Interview with Bruno Marquis

Head of Engineering and Procurement EDF Shenzhen Engineering,

Procurement, Generation and Research Center

Interview with Zhang Qiang, Chief Representative of ASME

Beijing Office and Executive Director of ASME Asia Pacific LLC

Technical Article

HAF Regulations

Events Calendar

EDITORS / 编辑

Arnaud Lefevre-Baril / 百力

Bessie Wang / 王文贝

NEWS / 新闻

Qi Jia / 戚佳

TECHNICAL ARTICLES / 科技文章


EVENTS / 展会会议

Qi Jia / 戚佳

DESIGNER / 设计师

FangHua Design Inc / 芳华设计公司

DYNABOND POWERTECH SERVICE /代邦核讯联系方式

Room 1509, Zhongyu Plaza, A6 Gongti North Road, Chaoyang District, Beijing, China

PHONE / 电话

+86-10-64681222

FAX / 传真

+86-10-64654957

EMAIL / 邮箱

[email protected]

WEBSITE / 网站

www.dynabondpowertech.com

Disclaimer

All rights reserved. No part of this publication may be reproduced in any form or by any means without the permission of its editors and/or its sources

Analysis of Dismantling Activities of Rotary Kiln for Benchmark Tests

mailto:[email protected]


5 Interview of the Month

6专访


DPS: Please tell us about your background?

Zhang Wenyin: My background is in nuclear engineering. I received a bachelor ’s degree from Shanghai Jiaotong

University, which is one of the best engineering schools in

China. I wrote several papers on nuclear reactor fuel reloading

and radioactivity protection.

DPS: How and when did you join Bureau Veritas?

Zhang Wenyin: After graduating, I joined Bureau Veritas in 2007 which I considered a great opportunity. By that time,

Bureau Veritas was elevating nuclear power as a strategic

market. We saw a strong potential development of this industry

after being frozen for 15 years. In 2005, China was already

starting its nuclear renaissance program and signed a major

agreement with Westinghouse for Sanmen and Haiyang.

BUREAU VERITAS was trying to further develop in this market

with our nuclear experience in China, and our technology and

expertise from Europe and the US.

DPS: Most of the students who graduate from Shanghai Jiaotong usually work directly for engineering and design companies. You are specialized in core design, why did you not join an SOE such as NPIC in Chengdu?

Zhang Wenyin: Just as you mentioned, design institutions, CGNPC, SNPTC can offer me a good platform where I can

develop well. But the reason I choose Bureau Veritas is that

it offers me a bettercareer planning. From here, I have the

opportunity to accumulate experience in industry practices

and get to know more about international technology, thermal

power, hydro power and petroleum and gas.IBureau Veritas

was established in 1994. At that time, the nuclear business was

not even an independent business unit like today, everything

was under the Power and Utilities business unit, which included

thermal, solar, wind and nuclear .

It was cool to be the first and only employee specialized in

nuclear power, but the loneness disappeared quickly. We soon

started to expand our nuclear business by recruiting our team

and providing a significant amount of training, we had our

experts coming from headquarters and the US to build the same

competences locally.

DPS: Regarding your training, have you been to your headquarters and the US as well or is everything done in China?

Zhang Wenyin: All training at was in China at the time I joined Bureau Veritas. However, I got the chance to go to the

US and France for advanced training after the nuclear business

unit was established. I was at the National Board of Boiler and

Pressure Vessel Inspectors (https://www.nationalboard.org),

I went to Columbus, Ohio for my training for the authorized

nuclear inspector endorsement. I am now a qualified trainer

for RCC-M code. I was also trained in some technical aspects

such as the European Technical Directives and Bureau Veritas

Shop Inspection. Here at Bureau Veritas, we are trying our best

to allocate all training resources to China. We can save a lot of

cost by doing that, and also benefit our localization process.

DPS: What makes you an expert in ASME certification?

Zhang Wenyin: The only way to become an expert is through study and accumulating abundant experience. Bureau

Veritas is one of the earliest agencies involved in the nuclear

ASME certification. We have more than one hundred ASME

Interview with Zhang Wenyin, Nuclear Power BU Manager, Bureau Veritas

Email: [email protected]: +86 180 1750 2088


certified pressure vessel manufacturers in China, and we have

presently several orders for ASME nuclear certification. We

are working for China’s AP1000 Project, which utilizes ASME

nuclear sections a lot. We also invested significantly in building

a Bureau Veritas training section for US code awareness, to

introduce the US codes and systems to our inspectors and train

them for related tasks.

DPS: How long did it take to become an inspector and later a trainer?

Zhang Wenyin: For simple work, it won’t take long to train an experienced staff into a qualified inspector. However for

nuclear industry, it really needs a long process. I have been with

Bureau Veritas for just over five years now and received 3 years

on-the-job training, which allows me to be a qualified inspector

in many fields. Some experts stayed with me at my work sites

so that I could sign reports, but everything was done under the

monitoring of our experts. This is how Bureau Veritas works -

we ensure the quality of our service and we train our inspectors

at the same time. This is the typical Bureau Veritas way of

balancing working time and training.

DPS: Which aspect of the training captivated you?

Zhang Wenyin: There is an old saying in China, which is that it is better to teach one to fish than to giving fish directly.

My mentor put in place a methodology as I did not have an

inspection background he not only teach me basic knowledge

but also show me how to understand and collect relevant

information independently, which benefits me a lot. At Bureau

Veritas you can either choose to become a generalist or an

expert in one area. As a generalist you can become a project

manager, coordinator, or join marketing and sales. Even though

I am specialized in nuclear I am a generalist.

DPS: Can you tell us what the main activities of Bureau Veritas are in the Chinese nuclear power market?

Zhang Wenyin: We are working with Westinghouse, Areva and Alstom on quality control and quality assurance. Regarding

the AP1000, for the four reactors in Sanmen and Haiyang,

we provided technical and quality assistance, QA audits to

all the suppliers, shop inspection and progress management.

We provided this service on behalf of Westinghouse. We are

working on the Yangjiang, Fuqing and Fangjiashan projects for

the emergency diesel generators. We are fully involved from the

workshop till the installation on site. We worked also in Lingao

1 and 2 for the reactor coolant pump, reactor vessels, reactor

internals and steam generator, also, we undertook the quality

inspection and quality assurance audit on behalf of Areva.

We carried out the inspection in Qinshan for the reactor head

replacement in 2007. This was part of our OPEX service, when

there is outage management or equipment replacement.

Regarding Qinshan, the client had very strong constraints

in terms of time and quality. The owner had to be sure the

manufacturing of the replacement part would follow its schedule

and quality; this is quite difficult especially when they face a

completed old technology with international standards. Bureau

Veritas is specialized in such challenging environments.

DPS: Do you provide similar services to CGNPC?

Zhang Wenyin: Our relationship with CGNPC is very good. CGNPC highly recognizes Bureau Veritas’s global

nuclear experience. We are proactively trying to expending our

cooperation.

DPS: And CNNC?

Zhang Wenyin: CNNC constructs many new projects - including, for example, Fuqing, Fangjiashan and Qinshan. We

work more on CNNC’s domestic projects.

DPS: Can you tell us about your inspection process in the transportation of nuclear equipment and other material?

Zhang Wenyin: We call this a full-process control, which is a special term used in Bureau Veritas. When the component

is nearing completion, proper packaging should be used

considering the transportation method (railway, road, sea). We

need to consider these criteria and check the packaging and

also the markings, making sure everything is in its corresponding

place, and in the right way. At the receiving site, we conduct an

inspection of the reception to make sure the component is still in


perfect condition.

DPS: Are you involved with imported equipment or domestic production?

Zhang Wenyin: We work for both. I would say we work more with imported components, as they require more complex

packaging and the owners, the EPCs are more cautious with

imported goods. Nevertheless, we want to get more involved in

domestic production like what we did for the AP1000. We have

already become very familiar with these manufacturers and

fully understand how they need to improve to fulfill customer

demand.

DPS: Are these requirements dictated by the EPC and/or the NNSA?

Zhang Wenyin: The NNSA gives instructions to the EPC directly, not to us. Bureau Veritas’ job is to ensure that all the

stakeholders follow all the requirements written by the EPC

strictly. Our responsibility is to check that every document and

implementation is in line with each other and they are validating

the requirements from the client.

DPS: Do you advise the EPC on the technical specifications?

Zhang Wenyin: We can provide consulting service and technical advice. In France we are an authorized agency

from the ASN (French Nuclear Safety Authority). We are quite

familiar with RCC-M, so we can advise AFCEN to adjust the

specifications based on our experience and feedback.

DPS: You recently joined the CNEA, could you tel l us the main reasons for this membership for Bureau Veritas?

Zhang Wenyin: CNEA is the biggest non-profit and non-governmental nuclear organization in China. Bureau Veritas has

accumulated abundant experience in supervision, inspection,

certification and qualification in nuclear industry and we have a

very experienced team. We are trying to provide our services

to the China nuclear renaissance and to expand with all the

domestic companies. Bureau Veritas hopes to walk shoulder

with shoulder with nuclear elite and share with them our

experience.

Bureau Veritas RCC-M Phase Ⅲ Training in 2007


Courtoy™

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GEA Process Engineering nv . Bergensesteenweg 186, 1500 Halle, Belgium . Tel. +32 2 363 83 00 . Fax +32 2 356 05 16 . [email protected]

GEA Process Engineering China Ltd . Hexian Road 99, 201109 Shanghai, PR China . Tel. +86 21 2408 2288 . Fax +86 21 2408 2222 . [email protected]

• Purpose-designed compression machines for uranium oxide and MOX•Machine design adapted for integration into glove box• Unique air compensator technology for high-precision pellet density control• New “constant density” control algorithm for fast machine set-upand highly accurate process control

• Automated in-line pellet density measuring with feedback to the press

• New high-performance powder feeding system• Hold-up / hold-down system for smooth ejection andavoiding cracks in pellets

• Proven reliability, with presses in operation in a nuclearenvironment for over 40 years

• Service teams based in Europe, USA and China

DPS: What hurdles did you face in China when you opened your new business unit in 2007?

Zhang Wenyin: We are luck to witness the rejuvenation of Chinese nuclear industry. We possess professional nuclear

knowledge and talents, we offer professional service. At the

beginning of our brand promotion, we encountered many

challenges. It will take some time to be fully understood and

accepted by Chinese nuclear market. At that time, China has

no special organization in charge of supervision, inspection,

qualification. And some activities, such as environmental

impact assessment, commissioning, operating services and

decommissioning, are only limited to appointed Chinese

institutions. Thus, although Bureau Veritas had accumulated

abundant international experience and with good performance,

we still need time to win a place in Chinese nuclear market.

DPS: Since the Fukushima accident , have you received requests regarding your services in environmental impact assessment?

Zhang Wenyin: There have been lots of changes since the Fukushima accident. It was an alarm for the Chinese nuclear

development. The industry realized that more control should

implement in the industry. Nuclear safety and nuclear quality is

much more important than how fast a project can be completed.

This is the basis of the nuclear culture, also a promise nuclear

industry should make to citizens. For Bureau Veritas it was a

chance and also a challenge, as we need to prepare well for

offering high-class service to meet the nuclear market demand.

We need to foresee demands from local companies and local

projects.

DPS: China does not have a rel iable domestic supply chain for safety related equipment . Are you involved in th is business?

Zhang Wenyin: Bureau Veritas specializes in helping suppliers improve their management systems. We received a

request recently and we help the owner and EPC to educate the

local manufacturer so they can become aware of the regulations

and code constraints. The Chinese suppliers have first-class

equipment in their workshops, they have their best machines

and they have highly educated employees from universities

and above. I would say that local manufacturer need support

to understand how to manage a good nuclear manufactory

and how to make sure their products and processes match the

quality requirements and schedule target of the owner.

DPS: The Chinese EPC relies mostly on French and US codes, the RCCM/RCCE and ASME/ IEEE. Do you provide any training related to the use of these codes?

Zhang Wenyin: We provide a lot of training on ASME and RCC codes. More important we have practical experience. I do

not think that an individual training course on standards would

have a long-standing effect for the client. Classroom training

cannot work at all. The purpose of the training is just to help our

clients understand the standard and improve their production

specification. We offer our clients the support in specification

and standards..

We helped YINHUAN Steel Company to get the certificate for

the ASME code. As for the RCC, we provide more training and

consulting.

DPS: One of your companies, OneCIS is an Authorized Insurance Agency that provides ASME Code Inspection Services; do you have more requirements since the AP1000 is the preferred choice of the third Generation NPP in China?

Zhang Wenyin: Bureau Veritas China is authorized to provide ASME related services in China. OneCIS is our

subsidiary, helping Bureau Veritas manage authorized inspection

business and inspectors. We are optimistic on our ASME

business. There are a large group of suppliers in China which

will bring more qualification business to us.

DPS: Could you tell us about your role in the AP1000 in China?

Zhang Wenyin: We are work ing on beha l f o f Westinghouse. We provided the site quality supervision and

quality assurance service. We provided on-site technical

assistance in the site’s construction and we provided the quality


Courtoy™

Global market leader incompression technology

for nuclear fuel pellets

engineering for a better world gea-ps.com/Courtoy

GEA Process Engineering nv . Bergensesteenweg 186, 1500 Halle, Belgium . Tel. +32 2 363 83 00 . Fax +32 2 356 05 16 . [email protected]

GEA Process Engineering China Ltd . Hexian Road 99, 201109 Shanghai, PR China . Tel. +86 21 2408 2288 . Fax +86 21 2408 2222 . [email protected]

• Purpose-designed compression machines for uranium oxide and MOX•Machine design adapted for integration into glove box• Unique air compensator technology for high-precision pellet density control• New “constant density” control algorithm for fast machine set-upand highly accurate process control

• Automated in-line pellet density measuring with feedback to the press

• New high-performance powder feeding system• Hold-up / hold-down system for smooth ejection andavoiding cracks in pellets

• Proven reliability, with presses in operation in a nuclearenvironment for over 40 years

• Service teams based in Europe, USA and China

surveillance and regular QA examination for the suppliers.

DPS: What is the t rend for Ch inese manufacturers? RCC-M or ASME?

Zhang Wenyin: This is a quite difficult question. For the RCC, the suppliers can get training quickly and most Chinese

suppliers have experience working with CGNPC, so they have

a program in place for the RCC system. The supply chain is

more mature with the RCC system, than for ASME, for example,

CNPEC provide training on the RCC code to their major

suppliers regularly. This is the main reason there is now more

demand for ASME training. As a supplier you have to be ready

for both standards.

DPS: Do you have any investment or involvement in the IFCEN?

Zhang Wenyin: We have investment in this education program for 5 years, starting from 2011. The intention of Bureau

Veritas is to be more involved in the development of talents in

China and get ready for the French-Chinese project. We do have

other programs in France as well for some Chinese students. It

is important to set up a connection between France and China

and we are proud to be part of this project.

DPS: Which other projects do you foresee in this market?

Zhang Wenyin: I believe the nuclear civil construction and outage services will have very big chance.

DPS: Do you have one piece of advice to give to a newcomer in China?

Zhang Wenyin: If you are a newcomer in China, you need to understand the culture and use a different approach, to

localize your team and plan your expansion in advance in China.

I would like to emphasize that understanding the local structure

and culture are the most important things.

Please download our magazine BV EXPRESS on http://www.bureauveritas.cn/wps/wcm/connect/bv_cn/Local/Footer/Home/

http://www.gea-ps.com/npsportal/cmsdoc.nsf/WebDoc/ndkw73fafk#.UaW7CdguEV4

10+Nuclear Operators

20+Countries

30+EminentSpeakers

100+Face-to face Meetings

150+Delegates

Endorsers：

Please Contact:Tel:+86(0)21 51920620Fax:+86(0)21 51920621 Email:[email protected]:www.innchinc.com/NITF2013

Steering Committee

Taghrid ATIEHHead, INIS UnitNuclear Information Section,Department of Nuclear EnergyIAEA

Sang-Hyung PARKGeneral ManagerInformation Technology OfficeKHNP

Yican WULeader, FDS TeamDirector, Insitute of Nuclear Energy Safety TechnologyChinese Academy of Sciences

Join Us Now!

Conference Highlights

Nuclear Information Technology(China)Forum 2013

1.Predict and Analyze the Trends of China’s Nuclear Industry Informatization2. Analyze China’s Nuclear Industry Informatiztion Features and Challenges3. Informative Project Showcases from the Nuclear Power Plants4. Updates on China’s Nuclear Software Self-reliance and Localization5. Latest Nuclear Informatization Related Technologies and Products Showcase6. Pre-arranged Face-to-face Meetings with Your Target Clients7. Precious Experiences from Industry Leaders Regarding the NPP Informatization Cases in and abroad

August 8th-9th, 2013Shanghai, China

——The FIRST&ONLY International Forum Specialized in Nuclear IT Industry


Interview with

Bruno MarquisHead of Engineering and Procurement EDF Shenzhen Engineering,

Procurement, Generation and Research Center

Email : [email protected] Mobile: +86 18200980713

DPS: When did you join EDF?

Bruno Marquis: I joined EDF in April 1995, and I

integrated the Nuclear Engineering Division (in French DIN

“Division Ingenierie Nucleaire”) in Lyon where I spent most of

my professional career before coming to China.

The expansion of EDF in China had a positive impact on my

professional career:

I was sent to China for the Ling Ao 2 project. CGNPC managed

the project and delegated some engineering support to CNPE

(CNNC Group). I was part of this team, which provided technical

support in project management and design review, in particular

for the safety and operation rules.

DPS: How long were you attached to CNPE?

Bruno Marquis: I stayed three and a half years in Beijing

then went back to France to work on the Taishan project as head

of System and equipment division, in SOFINEL (a JV between

EDF and AREVA involved in the design of Taishan Project).

DPS: You are the head of the PIAP E&P, what is the responsibility of the PIAP and your role?

Bruno Marquis: EDF created PIAP, a technical center

in order to have the entire nuclear technical scope of EDF

present in China. Its activity includes engineering, procurement,

operation and maintenance, and development. This center

supports the nuclear activities of EDF in China, such as project,

expertise, representation and technical lobbying.

I’m responsible for the Engineering and Procurement team.

DPS: How is your procurement activity organized?

Bruno Marquis: We are at the forefront. Our role

is to assess the Chinese market in coordination with our

headquarters in Paris. We are looking at Chinese solutions.

I take the example of obsolescence of equipment. The original

supplier disappeared or ceased production. We face a dilemma,

either to recreate the full supply chain for this component or

to look overseas, such as in China if there is not already an

existing solution. Why China? Because China has a nuclear

program similar to the one developed in France in the 1970s

and 80s. Due to the localization rate of the Chinese reactors,

such as the CPR1000, based on the French model, the Chinese

manufacturers follow the French standards and specification.

When EDF is looking for a spare part that is already obsolete in

France, we can find the spare part in China, manufactured with

French specification defined 25 years ago.

DPS: Who qualifies the supplier?

Bruno Marquis: EDF has a dedicated Operation

Technical Unit in charge of qualification. This unit assesses the

capacity of the suppliers to match our commercial, technical and

environmental requirements. This unit inspects and qualifies the

suppliers, according to the needs of EDF.

10+Nuclear Operators

20+Countries

30+EminentSpeakers

100+Face-to face Meetings

150+Delegates

Endorsers：

Please Contact:Tel:+86(0)21 51920620Fax:+86(0)21 51920621 Email:[email protected]:www.innchinc.com/NITF2013

Steering Committee

Taghrid ATIEHHead, INIS UnitNuclear Information Section,Department of Nuclear EnergyIAEA

Sang-Hyung PARKGeneral ManagerInformation Technology OfficeKHNP

Yican WULeader, FDS TeamDirector, Insitute of Nuclear Energy Safety TechnologyChinese Academy of Sciences

Join Us Now!

Conference Highlights

Nuclear Information Technology(China)Forum 2013

1.Predict and Analyze the Trends of China’s Nuclear Industry Informatization2. Analyze China’s Nuclear Industry Informatiztion Features and Challenges3. Informative Project Showcases from the Nuclear Power Plants4. Updates on China’s Nuclear Software Self-reliance and Localization5. Latest Nuclear Informatization Related Technologies and Products Showcase6. Pre-arranged Face-to-face Meetings with Your Target Clients7. Precious Experiences from Industry Leaders Regarding the NPP Informatization Cases in and abroad

August 8th-9th, 2013Shanghai, China

——The FIRST&ONLY International Forum Specialized in Nuclear IT Industry


DPS: EDF, Framatome and Novatome were the initial founders of the AFCEN (French Association for the rules governing the Design, Construct ion and Operat ing Supervision of the Equipment Items for Electro Nuclear Boilers). Is the AFCEN open to foreign organizations such as CNPRI?

Bruno Marquis: CGNPC is already a member of AFCEN,

any company can become a member, for example, Mitsubishi,

Westinghouse and most of the major nuclear companies have

joined AFCEN. The RCC code evolves all the time, the latest

version was published in 2012 and takes into account feedback

from the manufacturers, designers and operators. In that regard,

CGNPC joined AFCEN as a user of the code and is involved in

its development.

DPS: Most of the Chinese engineering companies use the RCC Code for their new reactors such as ACPR 1000, ACP 100, ACP 650 and ACP1000. Can we foresee China with its own code based on the RCC?

Bruno Marquis: China, like other countries such as

France, Japan, South Korea, the USA, Germany and Russia,

will certainly have its own code in the near future. In the 1980s

France used the ASME code as a basis for its RCC-M, it seems

clear that China will use existing codes to design its own. The

RCC is used by most manufacturers because it’s considered as

“freestanding” and independent. It is also very detailed and does

not require too much reference from third-party manufacturers,

such as in the ASME code for instance.

Chinese Nuclear specifiers could be considered as young

companies in this domain, with not so much experience in

nuclear design. So RCC-M provides part of a compulsory

standard in the manufacturing process. The ASME is not as

easy to use for new designers. I would not be surprised if

SNPTC, which is quite a young group, uses RCC-M parts as

additional specifications to the ASME code.

DPS: Is there a permanent or recurrent training for the RCC in China?

Bruno Marquis: When a manufacturer receives a

purchase order from EDF, Areva or any other company, the

requirements from the latest version of the code are generally

mandatory. The manufacturer can receive training from AFCEN,

or an accredited company such as Bureau Veritas or deal with it

by itself.

DPS: What is the involvement of SNPI (Suzhou Nuclear Power Institute) in RCC training?

Bruno Marquis: SNPI delivers some training on RCC-M

codes in China.

SNPI is in discussion with AFCEN to organize the user groups

of the RCC code in China.

DPS: Do you have any link with companies such as Bureau Veritas, Apave and Nuclear Academy, which are accredited by AFCEN in the Chinese market?

Bruno Marquis: The PIAP is not in the training business; however we have regular discussions in particular within events,

seminars, and conferences, organized by the association PFCE

(Partenariat France Chine Electricité).

DPS: Last March, AFCEN organized the triennial codes conference; more Chinese companies attended this conference, what is the main purpose of this event?Bruno Marquis: Indeed a large delegation of Chinese manufacturers and officials attended the conference, more than twenty persons, which is unique because AFCEN was not previously known as an international body. This shows how important the RCC code is in the Chinese market and how AFCEN is better recognized now in China.

DPS: Do you have any activity in the Taishan Project?

Bruno Marquis: The PIAP can be used as a support

unit, in conjunction with our back office in France, for EDF staff


working in CGNPC/EDF Taishan JV. Our Chinese engineers

which have been trained in France can also provide their

specific technical expertise to Taishan like the analysis of some

technical Chinese regulations and methods.

DPS: TNPJVC use the RSE-M 2010 code, can you tell us more about this?

Bruno Marquis: This is a code from AFCEN used

to monitor safety related equipment during operation. The

equipment must be qualified RCC-M. This code is used for

operating nuclear power plants. This means maintenance,

reparation and control of operating equipment at regular

intervals are codified, according to their safety role. This code is

used in France in all EDF nuclear plants

DPS: In 2010, France and China created the Sino-French Institute of Nuclear Engineering & Technology (IFCEN) in Zhuhai. Do you know if there will be some specific course dedicated to the RCC code?

Bruno Marquis: IFCEN’s dedication to the nuclear domain

started two years ago, according to the program, we foresee

a course in RCC code in 2014 or 2015 and this is a good

initiative from this institute. We have close relationships with the

management of this institute and are meeting the students to

offer them different nuclear jobs.

DPS: In terms of procurement, how do you foresee the fast growing Chinese market?

Bruno Marquis: The fast growing Chinese market is an

opportunity and a challenge for EDF and more generally for

the French industry. An opportunity to benefit from technology

development, a challenge to keep this growing market well in

line with our requirements.

In conclusion, I want say that EDF has to resolve specific

procurement concerns and China can provide some solutions,

but it is not in our intention to implement in China a full supply

chain in all market segments.

The nuclear power market is a long-term market. Any

manufacturer needs time to develop and qualify a product.

Technical expertise, and long-term after-sales services (we

operate during 40, even 60 years) are at the core of EDF

operator’s needs in terms of safety and availability.

China develops its own supply chain; nevertheless French

suppliers own a unique expertise and many French SME, for

instance the members of PFCE, that develop high-tech products

remain in the supply chain in China and all over the world

because they improve their quality processes and develop their

innovation capacity as well as their adaptation to the ever more

difficult qualification criteria.

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DPS: Could you briefly introduce your personal experience and your position in ASME to us?

Zhang Qiang: I used to serve in the former Machine

Building Ministry and then transferred to Chinese Mechanical

Engineering Society. In 2006, I joined ASME, taking the position

of the Chief Representative of ASME Beijing Office. Recently,

I took over the position as executive director of ASME Asia

Pacific LLC. to help with the popularization of service, activities

of the firm and promotion of our cooperation with Chinese

correspondent cooperative partners, including but not limited to

nuclear power.

DPS: What is the business scope of the ASME’s China Representative Office?

Zhang Qiang: China Representative Office of ASME was

officially founded in 2008. But in 2005, it had established a

Standard and Qualification Evaluation Union jointly with American

Petroleum Institute, American Society of Testing Materials and

the U.S. Section of Canadian Standard Association. At the end

of 2006, I came to ASME, serving as the chief operating officer

of the union with responsibility of the four institutes. After work

of the union finished and each organization had their individual

representative, I started to work in ASME for full-time. Currently

ASME gets four representatives in Beijing Office, which serves

in the field of energy industry, equipment manufacturing industry,

engineering technology field and education field.

To be precise, ASME Beijing Office function is functions as a

bridge introducing ASME and China to each other. Furthermore,

Interview with Zhang Qiang, Chief Representative of ASME Beijing Office

and Executive Director of ASME Asia Pacific LLC

E-mail: [email protected] Tel: 010-51096032

we hope to get real and positive information through our effort

to help cooperative partners to make the right choice, to realize

victories on foreground. Our business in China covers academic

activities, consultation service, training, publishing, organizing

conferences and seminars, and participating in exhibitions

by Chinese trade groups or associations. ASME’s Chinese

Representative Office has established good relationship with

the government, industry groups, colleges and universities and

relevant organizations. For instance: National Development

and Reform Commission, National Energy Board, the Ministry

of industry and information technology, the Ministry of Science

and Technology, the Ministry of Education, the National Nuclear

Safety Bureau, Chinese Mechanical Engineering Society,

China Machinery Industry Federation, Chinese Nuclear Society,

Tsinghua University, Shanghai electric company, Harbin electric

company, etc. And we are also in good relationship with nuclear

corporations like China National Nuclear Corporation, China

General Nuclear Power Corporation, State Nuclear Power

Engineering Company, etc.

Till July, 2012, there are 660 ASME licensed manufacturers

in Chinese mainland, 29 have nuclear certificates. Due to the

significant position of nuclear power in China, from now on,

we shall put emphasis on supporting nuclear construction,

establishment and perfection of Chinese nuclear standard,

establishment of more proper third-party inspection system and

perfection of nuclear security system. Also, we hope that through

our effort, American technology and industry fields and relevant

departments could conduct related work more closely.


D P S : H o w c a n w e t a k e p a r t i n t h e establishment and modification of ASME’s nuclear code and standard?

Zhang Qiang: ASME standard is an open system, with

access for everyone to join in and free for registration. Only one

different thing is that nonmembers are not entitled with voting

right before being officially admitted by relevant committees.

Concerning for the geographical location and operating customs,

ASME has made a special identification for expertise outside

North America, which called Aid Representative Scheme and

is equal with group membership. Because i It is impossible for

one person to participate ASME meeting every year, while on

behalf of a team, different representatives could take part in

the meeting annually, which can increase the possibility for the

team to participate in the regular meeting successively. The

main service objects of ASME could be precisely concluded as

“energy”, specifically, the first is petroleum and petrifaction, for

its demand of large number of pressure equipment supported by

ASME, and the second is the power station equipment, including

nuclear equipment.

With the need to advance with times and keep in accordance

with the economic development and practical situations, ASME

is revised on a large scale every two years. ASME has more

than 500 standardization committees, and four to five thousand

volunteers and experts joining in the modification and revisal

of ASME. There are two ways for official member of ASME to

take part in ASME activities: the first is attending the meeting

on oneself; the other is to participate in all-round-the-clock

through a software system called Code & Standard Connect

(C&S Connect). C&S Connect is a mixture of data platform and

foot platform, which displays the progress of the modification

and revisal of ASME standards clearly on this platform, allowing

the authorized ones enter in, browse the poll of ASME at real-

time, promote interactive communication and participate on the

internet vote for the final standard scheme.

Chinese experts can also take part in the establishment of

ASME code and standard, that is a positive interaction. ASME is

pretty thankful for Chinese organizations and experts to actively

contribute to the modification and revisal of ASME, which

indicates that ASME code and standard contains the intelligence

and experience of Chinese experts and as the technology

proceeding, we can see more contributions and louder voice

from Chinese organizations. I believe that also will be beneficial

to the establishment of Chinese nuclear regulations and third

party inspection system for China. Some organizations may

have difficulties in suddenly moving into such depth. We

provide other choices: one is work as contributive membership,

which means that the member can give advices only if he has

one, the other is as inspectors for which they will shoulder no

responsibility, of course, the authorized rights are also different.

I recommend Chinese organizations and departments to be

stronger and more courageous to motivate the experts into the

ASME activities, getting first-hand information, which will also

contribute to the fast development of Chinese nuclear industry.

DPS: Could you give us a brief introduction of ASME China International Work Group? What is its duty?

Zhang Qiang: ASME standard is followed by more than

110 countries across the world and recognized by more than

90 countries, some of which even directly take ASME code and

standard as the official and forceful standard and authentication.

It not only serves America, but also provides service for many

other countries. Recently ASME has made three missions for

itself: the first is to serve the energy issues; second, to carry

out the globalized functions; third, to cultivate talents, especially

training labors. We hope to create more convenient conditions to

help experts and units in non-North America regions to take part

in the ASME on international communication and cooperation, to

be the real components in the development and establishment

of ASME standard. We also hope to get more channels and

accesses to understanding, discussion, analysis and feedbacks

of the problems aroused during the use of ASME standard in

different places of the world. What’s more, we hope to establish

a new working mechanism to help different regions be more


pertinent in the action according to the real situations. That is

why we proposed the idea of International Work Group (IWG).

Work group is in accordance with different higher committee;

currently the established China International Work Groups is

correspondent to the third volume committee of Boiler Pressure

Vessel Standardization, also name nuclear volume. This work

group is both proposed by America and to a larger extent, by

China side realized about the need to get more knowledge of

the ASME standard during constructing new nuclear power

projects, introducing and absorbing the third generation of

nuclear power, especially developing its own third generation

nuclear power. That is why China also hopes to actively join

in the establishment and modification of the ASME standard,

in accordance with which the work group is built. As the

extension of the third volume committee, it has the right of

making speech, advising and explanations. By now, this work

group is gradually enriching its experience and improving its

work regulations, actively participating into the establishment,

modification and explanation of ASME related standards, and

in this way to support the nuclear power construction in China.

This international work group has 39 members, respectively

from government regulatory agencies, designing, project

construction and equipment manufacturing organizations,

including China National Nuclear Corporation, China Power

Investment Corporation, China Huaneng Group, Harbin Electric

Corporation, Shanghai Electric Corporation, Dongfang Electric

Corporation, China First Heavy Industries, China Second Heavy

Industries, Shanghai Power Equipment Research Institute,

Shanghai Nuclear Engineering Research and Design Institute,

etc. The secretariat is located in Shanghai Nuclear Engineering

Research and Design Institute.

This work group has been established for two years, during

which the meeting was held every three months, which works

very well with heated and serious discussion. The structure

of ASME committee and its Subordinate organization follow

the proportion of one third from designing and development

departments, one third from equipment manufacturing

department, and one third from customers units, and a

little proportion made up of supervisory organizations of

governments. The reason why we purposely maintain this

proportion is to guarantee that the ASME codes and standards

should be established with the principle of fairness, justice and

transparence. So as it always stays, the China work group is

basically in accordance with this proportion.

Each standard has its value of existence. China is also

developing its own nuclear standard. Through the possession

of its own independent intellectual property and nuclear power

station technique, China is enabled to establish a perfect nuclear

standard system. We sincerely hope that ASME code and

standard and Chinese nuclear standard can be fused together.

ASME standard is willing to serve for nuclear construction in

China and to make its contribution for Chinese standard system.

We get heavy responsibilities and there is a long way to go on

the Chinese nuclear standard construction, which need great

support from all walks of life. ASME is sincere in supporting

China to perfect its own code and standard system. When we

come to the responsibility and future way, I personally believe

that we shall start with the basic principles: First, standard

should come out of practice rather than Utopia or fantasy; then,

standard shall be established on the base of real democracy

and avoided being controlled by various interests; furthermore,

standard of China shall be in accordance with the demand of the

Chinese nuclear power development and the specific practice


of nuclear power construction; moreover, the government

shall play the leading role in the standardization process.

Chinese nuclear power construction is led by the government

as well as correspondent standard works. National Energy

Nuclear Power Standardization Committee, under the National

Energy Administration, is advancing its works steadily and the

framework of the standard is gradually getting complete. As

a model that establish standard in the way of administration,

Chinese progress can be seen clearly. If the government

totally retreats back, the whole situations will standstill for the

reason that we do not have solid ground in social intermediate

organizations, nor the real independent third party organization,

so the government with its supervision and financial support is

greatly important.

DPS: Does ASME plan to establish a nuclear standard for the Chinese nuclear market?

Zhang Qiang: ASME will not make a nuclear standard and

regulation special for China, but will cooperate with Chinese

organizations and experts, making further step to perfect the

ASME code and standard, for better service for Chinese nuclear

power construction. Two ASME committees have already set up

the China International Working Group (IWG) which is currently

in cooperation with the National Standardization Committee of

boiler pressurization in the preparation of the China International

Working Group of the eighth volume (pressure vessel)

Standardization Committee. Meanwhile, through negotiation

with several nuclear organizations, they also work together to

organize the China international Working Group of the eleventh

volume (in service inspection) Standardization Committee, in

order to add more Chinese elements into the ASME code and

standard. For the specific cooperation of the nuclear power

standard within China, ASME respects the views of China

side, and will provide cooperation as we have always done.

Personally I hope we shall take a detached attitude on judging

what kind of standard is more valuable to Human’s nuclear

construction.

As an international organization, ASME hopes to enhance the

communication with experts in China and more regions out of

the North America, come for more mutual agreement through

its platform. That is why ASME invites more organizations and

individuals getting into each committee of ASME. We hope more

IWGs be set up in China.

DPS: Do you have any suggestions on ASME’s future development in nuclear industry in China?

Zhang Qiang: I am not in seniority to give suggestions.

As a citizen, I hope that everything ASME does in China shall

be based on the principle of being practical and realistic and

serving people. Especially on security issues, we have to

hold a practical and serious attitude and avoid mistakes that

disappoint ourselves and others, because mistakes in nuclear

and electrical industry are too destructive to be compensated.

In the construction of nuclear power stations, serving people

shall be give top priority. My expectations and wishes to the

development of nuclear power is that we shall proceed step by

step, with a serious attitude and shall pay attention to and learn

from the way foreign countries do, and must figure out how it is.

We shall do as much as we can to send more young intelligence

to developed countries in nuclear power for study and training,

getting in depth into their core technology systems and getting

the essence. For the long-term development of Chinese nuclear

power, we shall plan properly and take slow pace, because

nuclear power construction cannot be done at one go.

DPS: Where is the difference of ASME and RCC-M? Whether ASME is suitable for AP1000 pile type only?

Zhang Qiang: ASME is the source of almost all the nuclear

power standards. RCC-M also derives from the boiler pressure

vessel specification of ASME. ASME specification lays more

emphasis on providing methods and platform to the users, in

order to carry out independent innovation based on their own

needs. The nuclear standard of ASME supports development of

20 Interview of the Month Hamon Thermal

www.hamon.com

Integrated solutions

for a clean environment

Hamon, the reliable choice.

HAMON THERMAL EUROPE (FR)Perspective Seine, Bâtiment C84, rue Charles Michels93284 Saint-Denis, FranceTel. +33 1 55 87 78 [email protected]

HAMON THERMAL AND ENVIRONMENTAL TECHNOLOGY (JIAXING) COMPANY LTD. 1st Floor of Building No.7, No.1369, South City Road 314000 Jiaxing, Zhejiang, China Tel. +86 573 8261 1908,[email protected]

Natural draft cooling towers: more than 300 references worldwide.

Hamon, World Leader in Engineering and Contracting, active since 1904.The Group has an unrivalled experience in development and implementation of cooling technologies for the power sector and other energy intensive industries. With numerousreferences in each cooling tower type, it has been confronted to any type of application. Hamon active R&D gives you the assurance of a state-of-the-art product.

all the nuclear technologies, not only AP1000.

DPS: Did the role and function of ASME have been changed since it enters Chinese market?

Zhang Qiang: The role and function of ASME does not

change so much compared to 1970s and 1980s, we have

obtained friendly acceptance at the beginning, and all of us

cherish the value of ASME, and spend a lot of energy to obtain

ASME certification. Many R&D institutions encourage their staffs

to participate various meeting of ASME and submit the paper.

The Special Equipment Supervision Bureau of National Bureau

of Quality Inspection arranges the auditor of their subordinate

body to intern in ASME, and many people have taken the

ASME authorized inspector examination since 1980s. Two

years ago, China Special Equipment Inspection and Research

Institute assigned more than 120 reviewers for examination

of the authorized inspector qualification, and set up the first

Chinese local authorized inspection agency. If there is any

change, we can say that we become more transparent, more

open to Chinese partners, and communicate with each other

more frankly, in this way, the decisions made by both parties

will be provided with better guarantee. In nuclear power field,

compare to the past, we have good relationship with the units

such as China National Nuclear Corporation, Chinese Nuclear

Society, China Nuclear Energy Association, State Nuclear

Power and China General Nuclear Power Company etc. As

the development of China’s nuclear power construction, the

demands for ASME codes are greater and greater.

DPS: What are the training and certificate authorities processed by ASME in Chinese nuclear power field?

Zhang Qiang: The Institute of Nuclear and New Energy

Technology in Tsinghua University is authorized by ASME in

training on nuclear standard and specifications in China. One

features of ASME training class is training small group for each

class consisted of no more than 25 people, which guarantees

each student have the chance to communicate with training

teacher. Training class in Tsinghua University is very regular and

efficient, which can really help students to solve problems, and

the training certificate is issued by ASME.

Other domestic units are also interested in becoming the

authorized training agency of ASME. However, considering the

factors such as training quality, input cost and time-consuming,

ASME is very cautious for approving more authorized training

agency. The training work of nuclear power industry is of

important significance, especially a considerable units and

projects use ASME standard and the relevant technical

documents, in case of key problems met, the answer shall be

found from ASME standards. Both the content and structure of

ASME standard is very unique, the ASME standard is required

to be explained by professional person, and training is an

effective manner. Sporadic patchwork understanding of a set of

standards is harmful, and correct understanding of the standard

shall be ensured through rigorous and strict training.

DPS: Currently, China’s nuclear power industry is of various standards, except ASME, there are French RCC-M, Russian standard and Canadian standard, what is your personal opinion? What is the impact of this on the nuclear power development in China?

Zhang Qiang: Various standards exist in China, and it

is difficult to make comments. But in my opinion, it is not a

good thing that various standards exist in a country, especially

for public investment projects, the coexistence of excessive

standard systems may consume greater material resources,

human resources and financial resources. The standardized

purpose is to be uniform, accurate and simplicity, which allows

various standards refer and adopt each other to avoid waste

of resources. The ASME standard is only one of the various

standards, and its authority is also verified through time and

practice.

21 Interview of the MonthHamon Thermal

www.hamon.com

Integrated solutions

for a clean environment

Hamon, the reliable choice.

HAMON THERMAL EUROPE (FR)Perspective Seine, Bâtiment C84, rue Charles Michels93284 Saint-Denis, FranceTel. +33 1 55 87 78 [email protected]

HAMON THERMAL AND ENVIRONMENTAL TECHNOLOGY (JIAXING) COMPANY LTD. 1st Floor of Building No.7, No.1369, South City Road 314000 Jiaxing, Zhejiang, China Tel. +86 573 8261 1908,[email protected]

Natural draft cooling towers: more than 300 references worldwide.

Hamon, World Leader in Engineering and Contracting, active since 1904.The Group has an unrivalled experience in development and implementation of cooling technologies for the power sector and other energy intensive industries. With numerousreferences in each cooling tower type, it has been confronted to any type of application. Hamon active R&D gives you the assurance of a state-of-the-art product.

22HAF Regulations

Chapter 1: General Provisions

Article 1- To better regulate the qualification of civil nuclear safety welders and welding operators and to ensure the welding quality of civil nuclear equipment, the HAF603 regulation is formulated and introduced, following the guidelines in Supervision and Management Regulations for Civilian Nuclear Equipment (HAF601).

Article2- The HAF603 regulation applies to qualification management of civil nuclear safety equipment welders and welding operators.

Article 3- Anyone who intends to work as civil nuclear safety equipment welder or welding operator must pass welding examination and obtain certificate before they can conduct nuclear safety welding activities.

Chapter 2: Agencies and responsibilities

Article 4-The national nuclear safety regulatory department under the State Council is responsible for the evaluation and certificate issuing to qualified welders and welding operators. It mainly conducts:

To set up examination center

To prepare the examination content including the guidelines, basic theories and then organize examination.

To oversee the assessment and evaluation of the test results

To review of the plan and result of the examination center and then to issue certificate to qualified welders and welding operators.

Archive related information about welding certificate holders.

The nuclear safety regulatory department under the State Council can set up a committee according to the need to evaluate the qualification of the welding certificate holders and perform other responsibilities.

Article 5- The national nuclear safety regulatory department will select an examination center among entities who can meet

C iv i l i an Nuc lear Sa fe ty Equ ipment We lder Qualification Regulation ( HAF603)

the following requirements. The potential examination center must have:

Quality assurance about its examination system, a complete set of assessment and management rules, an examination treasury and a robust procedure for welding examination.

Above 5 years experience in the welding examination business and the total number of exam takers must be more than 300.

Exam venues where examination activities can be conducted, including skills operation test site which can hold at least 20 seats, room for theory test, welding materials inventory and database etc.

Welding test evaluation equipment including electrode and flux drying equipment, welding specimen, tools that can make welding specimen, physical inspection and nondestructive testing equipment.

Examination panel including above 3 professional full time welding engineers. Two full time inspectors with nuclear Ⅱ level on nondestructive test.

Ability to organize examination and to archive the files of of welders and welding operators.

Article 6- The examination center will be responsible for organizing the examination on theoretical knowledge and operational skills on nuclear equipment welding. Procedures include:

• Make examination plan.

• Assess the basic qualification of the exam takers.

• Determine the specific examination content of theoretical knowledge and practical skills

• Prepare test specimen and assessment tools to evaluate the examination results

• Formulate or determine the welding procedures for examination

23 HAF Regulations

• Establish and manage files of welding certificate holders

Article 7- welding exam takers must meet the following requirement

• Above middle school degree.

• Healthy

• Can following the welding procedures

• Can perform welding activities independently

Chapter 3: Examination content and methods adopted

Article 8- examination content includes theoretical knowledge and practical skills

Article9-the theory part includes general theoretical knowledge and specific theoretical knowledge

Potential welders on special welding methods and special welding materials must pass theoretical test before they can take practical test.

The validity period of the theoretical certificate is three years.

Article 10- the theory examination content should include:

• Basic knowledge in nuclear power system( radiation protection) and quality assurance

• Civil nuclear safety equipment knowledge including category and safety levels of nuclear equipment, manufacturing standard and welding guidelines, principles and requirement on welded joints, commonly used base metal and welding consumables, characteristics of welding methods and key manufacturing technologies (knowledge in heat treatment and non-destructive testing)

• Knowledge in welding device, device assemblies, gauges and maintenance.

• Knowledge in the classification, properties and influence factors of welding joints, welding code and pattern

• Causes of welding defects and knowledge to prevent them

• Causes of welding stress and deformation and knowledge to prevent them

• Knowledge in safe welding

Article 11- the examination content in the specific welding theory part should be made according to the special methods and special material.

Article 12-examination centers should determine the examination items based on the welding methods, sample forms, parent material type, welding materials, welding forms, welding position, specimen size and specifications, welding elements (pads, single-sided welding, and double-sided welding), etc.

Article 13-in the practical test part, the number of welding items is set beforehand. The practice of choosing the best welding result among multiple welding tests is forbidden.

The preparation of testing sample and welding process should meet following requirement:

1. The surface of weld groove and 25mm field on both sides of weld groove in examination specimen should be clean, it need to clean up all the iron filing, oxide, oil, rust, dirt and other sundries.

2. The welding bar and the welding flux should be dried to the degree required and can be obtained anytime. The welding wire should be rid of oil and rust.

3. Exam takers should conduct welding test according to procedures approved

4. The code of the exam taker should be pasted on the welding sample before the examination in the presence of member of the exam center, invigilator and the exam taker himself.

5. Horizontal fixed specimens and 45 ° fixed specimen should be marked the hour marks on the welding position, Weld positioning is not permitted to weld in the "6" mark; Pipe down welding specimen shall be in accordance with the hour mark to locate the fixed specimens, and only can start to arc in the “12”mark, end arc in the “6” mark; up welding should arc in the “6” mark.

6. There is at least a arc ending and then welding joint in the first layer of welding line in all the examination specimens; when testing the welding operator, it is not permitted to end arc in the middle of each welding line.

7. In the welding examination, it is allowed to add some arc plates and extraction plates.

8. When specimen welding started, welding position shall not be

24HAF Regulations

changed; for pipe and tube butt weld 45 ° fixed plate specimen, the angle between the horizontal plane and tube axis should be 45 ° ± 5 ° range.

9. It is not permitted to do grinding and rework in the last layer in the surface of examination specimen.

10. The forms and dimensions of specimen welding groove should be prepared in accordance with welding procedures, or by the assessment center in accordance with the appropriate preparation of national standards and industry standards.

C h a p t e r 4 : Te s t r e s u l t s e v a l u a t i o n , certification and management

Article 14-the full scores of both the basic theoretical knowledge test and the specific theoretical test are 100 and scores of above 60 can be classified as qualified

Article 15-exam takers pass practical skills test when their welding samples pass evaluation.

Article 16-in the team-up examination, if the exam result is below the 60 scores (not qualified), the exam taker will not pass the exam if he can be identified. However if not, all exam takers in the team will be classified as not qualified.

Article 17-Practical skills exam takers have a second chance in one month to take the exam. If he cannot pass in the second time, he will have to wait for at least three months before he can take the exam.

Article 18-examination center should keep record the test result of every exam taker and the evaluation result of the welding sample

Exam center should submit to the national nuclear regulatory department the exam result of qualified welders and welding operators within ten days when they finish the evaluation of the exam result

Article 19- civil nuclear safety welders and welding operators conduct welding activities corresponding to the activities they passed in the exam.

Article 20- exam center should keep record of every quailed welders and welding operators. The record should include their welding procedures.

Employers who employ welders and welding operators should keep record of welding activities and submit the record to the

exam center every six months

Article 21- National nuclear regulatory department should complete the inspection of the exam result within 20 days upon receiving the exam result from the exam center and decide to issue the certificate or not.

National nuclear regulatory department will issue certificate to qualified exam takers within 10 days once the decision is made.

Article 22- certificate to qualified welders and welding operators should include:

• Name of the welder or welding operator and the employer

• Exam items passed

• Certificate validity period

• Certificate code

Article 23- certified welders or welding operators are forbidden to work for two or more employers at the same time.

In the event of changing employer, new employer of certified welders or welding operators should submit certificate renewal application to exam center with comments of original employer of the welder or welding operator. The national nuclear regulatory department will evaluate and decide if the certificate can be renewed. Validity period of the new certificate is the same to the old certificate.

Article 24- validity period of welding certificate is 3 years

Certificate holders planning to renew the certificate should apply to the exam center 60 working days before the validity deadline.

The exam center should complete the evaluation of the application and make suggestion on whether to renew or not within ten days upon receiving the application and then summit the suggestion and record of the applicant to national nuclear regulatory department who should make the final decision to renew or not the certificate before the validity deadline. Twelve months will be given to those whose renewal application passed evaluation from the validity deadline.

Those who qualification cannot meet the certificate renewal requirement can renew their application if they plan to continue working in the welding industry

Article 25- certificate will be invalid automatically if the holder suspended welding activities for above three months.

Article 26-exam evaluation report and qualified welding items in the qualification certificate should be coded. The combination code sequence should be welding method code, welding sample

25 HAF Regulations

code, welding type code, parent material code, welding material, size of welding sample, welding location and welding elements code.

Article 27- Foreign certified welders or welding operators should get permission from national nuclear regulatory department before they can conduct civil nuclear welding activities in China.

Article 28- certified welder or welding operator who was found guilty of fraud will be revoked of its qualification and cannot take exam within one year.

Chapter 5: supervision and inspection

Article 29- Examination center should inform the national nuclear regulatory department in writing of the exam plan, exam content and exam site ten days before the exam date.

Article 30- the national nuclear regulatory department will inspect the evaluation and management work of the exam center.

The inspection work will have two parts, comprehensive inspection and specific inspection:

Comprehensive inspection will include the quality assurance system of the exam center, faculty staff, evaluation and management system, related document for evaluation, evaluation plan and implementation

Specific inspection will include random sampling of welding test results

Article 31- Exam center should cooperate with national nuclear regulatory department in conducting inspection by providing true information and necessary materials. Exam center will not refuse or hamper inspection.

Chapter 6: Legal Responsibilities

Article 32- Any breach as depicted in the following situation, the exam center will have to stop and adjust according to requirement of national nuclear regulatory department. In the worst case scenario, the exam center will be revoked of exam qualification.

• Change in the condition exam center can provide to meet the requirement prescribed.

• Failure to comply with the requirement described HAF603 regulation

• Refuse or impede inspection of national nuclear regulatory department

• Confusion in work management and poor quality of examinations

• Serious breach of regulation and fraud

Article 33- Anyone in the exam center who has the following behaviors will be revoked of its examination qualification and also be subject to the related law and regulation.

• Divulge the exam content

• Commit fraud in the examination process

• dereliction of duty, negligence which lead to confusion during the exam and inaccuracy of exam result

Article 34- Any civil nuclear equipment manufacturer, installation company or nuclear power operator who provide fake letter of proof will be fined 10 to 30 thousand RMB.

Article 35- Civil nuclear welding certificate holder who conduct welding activities beyond the his certification qualification will be suspended by national nuclear regulatory department and will be penalized according to the Article 49 in the Supervision and Management Regulations for Civilian Nuclear Equipment (HAF601).

Article 36- Anyone who make up fake civil nuclear welding certificate will be detained for 10 to 15 days and be fined 1 thousand RMB according to the Article 52 in the Regulations of the PRC on Administrative Penalties for Public Security. If the adverse effects are minor, offender will be detained for 5 to 10 days and be fined below 500 RMB.

Article 37-welders or welding operators who failed to follow the welding procedures which caused severe quality problems will be revoked of their certificate by the national nuclear regulatory department.

Chapter 7: Supplementary Articles

Article 38-The content, method and assessment criteria of the examination on other welding methods and welding materials will be made by the company and the exam center according to their design and manufacturing requirement. And the exam scheme will also be reported to the national nuclear regulatory department.

Article 39- The Civilian Nuclear Safety Equipment Welder Qualification Regulations (HAF603) will come into force from January 1st, 2008. The old Civil Nuclear Pressure Equipment Welder, Welding Operator Training, Examination Management Regulations (HAF603) passed by National Nuclear Safety Administration on June 6th 1995 would be abolished.

26HAF Regulations

• Meet top level industry leaders• Increase your brand recognition within the marketplace• Create new partnerships and alliances• Develop relationships through new networking opportunities

EVENT BRIEF:Currently, the use of nuclear power is increasing around the world; nuclear electricity already represents the primary part in electricity production. As people get more and more concerned about the greenhouse effect and climate change, nuclear energy as a low-carbon option provides reliable electricity, can play an important part in the energy mix and is becoming an increasingly important part of a clean energy future. To meet our nation’s need for dependable, safe and sustainable electricity, actively promoting nuclear power construction has become one of our nation’s key energy development strategies. It is important to realize our goals of protecting our environment, optimize the electricity industry structure and improve our nation’s comprehensive economic strength and technology level, and enhance our international status.

On 24 October, 2012, the State Council of China finally approved the Nuclear Safety Development Plan and Medium and Long-Term Nuclear Power Development Plan, officially stride forward one step to the restart of NPPs construction in a safer and moderate way. According to WNA’s prediction, China’s nuclear capacity will achieve 67.3 GW by 2020.

To further explore China’s nuclear power policy in the post-Fukushima age, discuss strategies to safely and effectively develop nuclear power, draw attention to the status of the new project approval process, preview China’s future nuclear power safety planning, exchange advanced nuclear power equipment manufacturing technology, the 8th China Nuclear Power Congress will be held in Weihai, Shandong Province on July 4th & 5th, 2013.

8th Annual China Nuclear Power CongressJuly 4th& 5th, Yantai, Shandong Province, China

The Annual Conference offers unparalleled opportunity to connect with the most influential executives to develop long term business partnerships and showcase your organization’s talents and expertise within the industry.The Conference attracts the most active player in the market, giving you the opportunity to strengthen your market share, increase your brand recognition and achieve business growth.

For More Information Contact:Sharon ChenTelephone: +86 21 6085 1000 ext.313Mail: [email protected]: http://www.noppen.com.cn/upcoming/L1313/CN/index.asp

Event Highlight:

Exclusive opportunities available!

Testimonials “Rich in content” --Nuclear Power Institute of China

“Well organized, excellent speeches.”--China Guangdong Nuclear Power Holding Co Ltd

“Had involved in many different levels of nuclear industry chain, viewpoints are quite clear”--China Nuclear Power Engineering Co Ltd

“Gained new knowledge in several areas. Very insightful” -- International Atomic Energy Agency

Organizer:

27 Events Calendar

June

2013 Shanghai International Pump & Valve Exhibition

Date: 2013/06/05-2013/06/07Add: Shanghai World Expo Exhibition & Convention CenterContact: Zhou XingshuTel: 021-33231318Website: http://expo.flowex.com.cn/expo/index.php

The 9th China (Beijing) International Power Transmission & Control Technology Exhibition 2013

Date: 2013/06/28-2013/06/30Add: Beijing International Exhibition CenterContact: Beijing Huamao Exhibition Co., Ltd.Tel: 010-57532076Website: http://www.ciptc.org/

The 9th Asia International Industrial Automation Exhibition, 2013

Date: 2013/06/28-2013/06/30Add: Beijing International Convention Center (san yuan qiao)Contact: Wang PengTel :13520851746Website:http://www.expo-china.com/pages/exhi/201210/62173/exhi_detail_gaikuang.shtml

Beijing

Chengdu

Yantai

Shanghai

ShenzhenGuangzhou

Hunan

Events Calendar

Asia International Intellect Equipment Manufacturer Industry Exhibition, 2013

Date: 2013/06/28-2013/06/30Add: Beijing International Convention CenterContact:Li BinTel: 18601148935Website: http://www.aiacte.com/Channel.asp?ChannelID=41

Central China International Equipment Manufacturing Exposition

Date: 2013/06/27-2013/06/30Add: Hunan International Convention CenterContact: Lei XiaolinTel: 0731—82865666 Website: http://www.ccieme.com.cn

The 17thHuanan Industry Control Automation International Exhibition

Date: 2013/06/26-2013/06/28Add: Guangdong Shenzhen Exhibition CenterContact: Fan SaijuTel: 020-61198837Website: http://www.iaexpo.org

• Meet top level industry leaders• Increase your brand recognition within the marketplace• Create new partnerships and alliances• Develop relationships through new networking opportunities

EVENT BRIEF:Currently, the use of nuclear power is increasing around the world; nuclear electricity already represents the primary part in electricity production. As people get more and more concerned about the greenhouse effect and climate change, nuclear energy as a low-carbon option provides reliable electricity, can play an important part in the energy mix and is becoming an increasingly important part of a clean energy future. To meet our nation’s need for dependable, safe and sustainable electricity, actively promoting nuclear power construction has become one of our nation’s key energy development strategies. It is important to realize our goals of protecting our environment, optimize the electricity industry structure and improve our nation’s comprehensive economic strength and technology level, and enhance our international status.

On 24 October, 2012, the State Council of China finally approved the Nuclear Safety Development Plan and Medium and Long-Term Nuclear Power Development Plan, officially stride forward one step to the restart of NPPs construction in a safer and moderate way. According to WNA’s prediction, China’s nuclear capacity will achieve 67.3 GW by 2020.

To further explore China’s nuclear power policy in the post-Fukushima age, discuss strategies to safely and effectively develop nuclear power, draw attention to the status of the new project approval process, preview China’s future nuclear power safety planning, exchange advanced nuclear power equipment manufacturing technology, the 8th China Nuclear Power Congress will be held in Weihai, Shandong Province on July 4th & 5th, 2013.

8th Annual China Nuclear Power CongressJuly 4th& 5th, Yantai, Shandong Province, China

The Annual Conference offers unparalleled opportunity to connect with the most influential executives to develop long term business partnerships and showcase your organization’s talents and expertise within the industry.The Conference attracts the most active player in the market, giving you the opportunity to strengthen your market share, increase your brand recognition and achieve business growth.

For More Information Contact:Sharon ChenTelephone: +86 21 6085 1000 ext.313Mail: [email protected]: http://www.noppen.com.cn/upcoming/L1313/CN/index.asp

Event Highlight:

Exclusive opportunities available!

Testimonials “Rich in content” --Nuclear Power Institute of China

“Well organized, excellent speeches.”--China Guangdong Nuclear Power Holding Co Ltd

“Had involved in many different levels of nuclear industry chain, viewpoints are quite clear”--China Nuclear Power Engineering Co Ltd

“Gained new knowledge in several areas. Very insightful” -- International Atomic Energy Agency

Organizer:

28Events Calendar

The 14th Guangzhou International Die Casting & Industrial Furnace Exhibition

Date: 2013/06/16-2013/06/18Add: Ground Floor, B Area, China Import and Export Fair Pazhou ComplexContact: Mei WenTel: 18002266711Website: www.foundrychina-gz.com

The 14th Hunan Haobo International Industrial Automation & Instruments Exhibition

Data : 2013/06/27-2013/06/30Add: Hunan International Convention CenterContact: Lei XiaolinTel: 0731—82865666 Website : http://www.ccieme.com.cn/inner-zz.asp?Pid=64

CIPTC the 9th China (Beijing) International Power Transmission & Control Technology Exhibition, 2013

Data:2013/06/28-2013/06/30Add: China International Exhibition CenterContact: Yu JiaTel: 13691595976Website:www.ciptc.org

July

8th Annual China Nuclear Power Congress

Date: 2013/07/04-2013/07/05Add: Yantai, Shandong ProvinceContact: Sharon CHENTel: 021-60851000-313Website: http: //www.noppen.com.cn/upcoming/L1313/CN/index.asp

Grid Tec China 2013 Sustainable Solutions for China’s Energy Future

Date: 2013/07/03-2013/07/05Add: China National Convention Center, BeijingContact: Kong XiangyongTel: 13501209274Website: http://en.gridtecchina.com/

Central and Western China (Chengdu) International Environmental Protection Technology and Equipment Show 2013

Date: 2013/07/18-2013/07/20Add: The New International Exhibition Center of Chengdu Century CityContact: General Manager WangTel: 029-88216136Website: http://www.qixingkji.com/

China (West) International hot working Industrial Expo 2013

Date: 2013/07/18-2013/07/20Add: The New International Exhibition Center of Chengdu Century CityContact: Zhang LuTel: 15529020053Website: www.cwieme.com

August

The 24th Internat ional Conference and Fair for Measurement Instrumentation and Automation

Date: 2013/08/27-2013/08/30Add: China International Exhibition Center Contact: Ms. ZhangTel: 86-10-82800630Website: www.miconex.com.cn

Platts 4th AnnualSmall Modular Reactors ConferenceManaging the Technical, Cost, and Regulatory Challenges to Develop a New Nuclear IndustryMay 29-30, 2013 • Mandarin Oriental Hotel • Washington, DC

This is the leading conference on small modular reactors in the United States. Meet with the leading companies and experts on development of small modular reactors, from the USA and from around the world.

Hear These Case Studies and Updates on Development:• B&W mPower • Westinghouse• NuScale Power

Confirmed Speakers Include:• Warner Baxter, President and CEO, Ameren Missouri• Barry Hart, CEO, Association of Missouri Electric Cooperatives• Christofer Mowry, President, Babcock & Wilcox mPower, Inc.• Geoffrey Black, Chairman, Department of Economics, Boise State University• Marcel deVos, Senior Project Officer, Canadian Nuclear Safety Commission• Sharon Squassoni, Director, Proliferation Prevention Program, CSIS • Donald Hoffman, President and CEO, EXCEL Services Corporation• Greg Halnon, Director, Regulatory Affairs, FENOC• Andrea Jennetta, Publisher, Fuel Cycle Week • Mark J. Harper, Water Reactor Technology Development, IAEA• Mike McGough, Chief Commercial Officer, NuScale Power• Randy Beatty, Distinguished R&D Staff, Oak Ridge National Laboratory• Mark Herlach, Partner, Sutherland Asbill & Brennan LLP• Daniel Stout, Senior Manager SMR Technology, TVA• Anna Bradford, Chief, SMR Licensing Branch 2, US NRC• Edward McGinnis, Deputy Assistant Secretary, US Department of Energy• John Kelly, Deputy Assistant Secretary, US Department of Energy• Craig Welling, Advanced Reactor Concepts, US Department of Energy • Jonathan Hinze, SVP International, Ux Consulting • Kate Jackson, Chief Technology Officer, Westinghouse Electric Company

See web site for details: www.platts.com/smallmodularreactors

30 Technical Article

Technical Article




Mitsuo TACHIBANA, Sari IZUMO, Noritake SUGITSUE, Seung-Kook PARK

Japan Atomic Energy Agency: Tokai-mura, Naka-gun, Ibaraki 319-1195, Japan, [email protected]

Korea Atomic Energy Research Institute:150-1 Dukjin-dong, Yuseong, Daejeon, 305-353, Korea, [email protected]

INTRODUCTION

The agreement for cooperation in the field of peaceful uses of nuclear energy between Japan Atomic Energy Agency (JAEA) and Korea Atomic Energy Research Institute (KAERI) was signed in 2008. The agreement was included the field of Dismantling and Decommissioning (D&D). Technical information exchange meetings concerning the field of D&D have been conducted under the agreement every year.

Each organization has uranium conversion facilities (CF). JAEA has the Uranium Refining & Conversion Plant (URCP). KAERI has the Uranium Conversion Plant (UCP). These CFs have been under decommissioning after their missions completed. Each organization has been developing decommissioning engineering systems to develop effective decommissioning plans and to implement dismantling activities effectively. JAEA has Decommissioning Engineering System for Nuclear Faci l i t ies (DENESYS). KAERI has Decommissioning Engineering System (DES).

Therefore, benchmark tests were started in order to verify mutual decommissioning engineering systems.

At first, each organization compared mutual decommissioning engineering system. At second, each organization compared specification and dismantling procedure of the rotary kiln and management data for dismantling the rotary kiln. At third, management data for the rotary kiln plan to be calculated by using mutual decommissioning engineering system. As of now management data for dismantling the rotary kiln in KAERI was calculated by using DENESYS of JAEA.

This report describes results of comparisons of dismantling activities of the rotary kiln in JAEA and KAERI, and calculated results by JAEA.

OUTLINE OF D&D OF CFS

JAEA has URCP in the Ningyo-toge of western part of Japan.

KAERI has UCP in Daejeon of center part of KOERA. Then, these CFs have been under decommissioning after their missions completed.

D&D of URCP in JAEA

URCP was constructed in JAEA in 1981, which was a three-story building, with a total radiation controlled area of 7,300m2. URCP has the wet conversion facility where yellow cake is converted into UF6 and the dry conversion facility where reprocessed uranium (UO3) is converted into UF6. URCP was operated from 1982 to 1999. About 750tons of UF6 were produced for 20 years in URCP.

Equipment of the wet conversion facility in URCP was already removed from FY2000 to FY2001. (1) Dismantling activities of the dry conversion facility in URCP was started in 2008. (2)

Firstly, equipment concerning uranium process was dismantled in September 2011. Fluidization media storage underground tank, neutralization, precipitation system and ventilation system will be dismantled from FY2012.

Dismantled waste was temporally stored in URCP. About 470tons of equipment was removed from 2008 to 2011. Manpower for dismantling activities was about 12,000man-days.

D&D of UCP in KAERI

UCP was constructed in KAERI in 1982, which was a three-story building, with a total radiation controlled area of 1,981m2. UCP has Ammonium Di Uranate (ADU) process and Ammonium Uranyl Carbonate (AUC) process. UCP was used to produce 100tons of UO2 powder a year for the Wolsong-1 CANDU reactor. UCP was shutdown in 1992. (3)

Decommissioning work was started in 2004. The project scope are to dismantle all equipment, to decontaminate dismantled metal waste and inside of building, to remove contaminated soil, to treat lagoon sludge waste, to decontaminate lagoon


structure, and to perform final radiological survey of the building and the site. The building will be released for reuse after finishing the decommissioning work.

The decommissioning work was completed in 2011. About 379tons of radioactive metal and concrete waste was generated. The releasable waste was 143tons respectively. Manpower for dismantling activities was about 13,875man-days.

DECOMMISSIONING ENGINEERING SYSEMS

Each organization has been developing decommissioning engineering systems. JAEA has DENESYS, which has been developed to provide useful information, to develop effective decommissioning plans and to implement dismantling activities effectively. KAERI has DES which has been developed to provide useful information for making decommissioning plan & design, licensing, setting up dismantling procedure.

Outline of DENESYS in JAEA

DENESYS consists of 4 evaluation systems: Project management data evaluation code for dismantling activities (PRODIA code), radiation exposure estimation code for dismantling activities (REX code), residual radioactive inventory calculation in decommissioning nuclear reactor (RADO code) and simplified decommissioning cost estimation code (DECOST code).

PRODIA code can evaluate manpower and amount of waste based on relationship between weight of equipment and manpower and dismantling scenario. REX code can evaluate public and worker doses with a transportation model of radioactive material released by cutting equipment. RADO code can evaluate neutron effluent and activated inventory based on facility operation history and material component data. DECOST code can evaluate decommissioning cost based on simplified models using the relationship between manpower and weight of equipment.

Outline of DES in KAERI

DES consists of 4 systems: Decommissioning facil i ty characterization DB system (DEFACS), decommissioning modeling system (DEMOS), decommissioning information system (DECOMMIS) and decommissioning work-unit productivity calculation system (DEWOCS).

DEWOCS is to get evaluated factors concerning decommissioning work-unit productivities. DEWOCS use data from DECOMMIS and DEFACS and actual experienced data from a decommissioning

site. The evaluated factors will be used for planning of nuclear facility decommissioning.

DEMOS is to set up items for decommissioning of new objective facility, to estimate decommissioning cost and manpower consumption according to work properties, to calculate using time and cost on dismantling, decontamination and waste management devices, to estimate manpower and duration. DEMOS use factors from database of DEWOCS as of the decommissioning work-unit productivities, labor costs, fee of devices and actual experienced data from decommissioning site.

COMPARISON DISMANTLING PROCEDURE FOR ROTARY KILN IN JAEA AND KAERI

The rotary kiln was selected as an object of the benchmark tests. The rotary kiln of URCP in JAEA was used to operation for crushing and drying yield uranium (UF4) in order to store yield uranium stably in 200L drum at a long-term. On the other hand, the rotary kiln of UCP in KAERI was equipment for ADU process. Table I shows specification concerning the rotary kilns of URCP in JAEA and UCP in KAERI.

Firstly, dismantling procedure and management data of dismantling activities concerning the rotary kiln were analyzed for benchmark test as follows.

Table I. Specification concerning the rotary kilns of URCP in JAEA and UCP in KAERI

URCP in JAEA UCP in KAERI

Rotary kiln

Name Rotary kiln Hydro fluorination

(X-S130) rotary kiln (263-25)

Material SUS SUS

Size φ500 x 3,950 mm φ268 x 5,840 mm

Weight 2,700 kg 3,000 kg

Room in which rotary kiln was installed

Name UF4 processing room Kiln room (6210)

Size 12.0 x 12.0 x 6.5 m 5.4 x 14.0 x 3.4 m

Total weight of equipment (without pipes, valves, cables) 14,942 kg 8,519 kg


Fig. 1. Rotary kiln of URCP in JAEA.

Dismantling Procedure of Rotary Kiln in JAEA

The rotary kiln was installed on the cradle for the rotary kiln on the UF4 processing room in 2nd floor of URCP as shown in Fig.1. The rotary kiln was connected to a crasher, a hood for collected powder, an intermediate receiver, and a screw feeder.

Firstly, the cover of the rotary kiln was removed. The rotary kiln was unloaded from the cradle. After unloading the rotary kiln, the cradle was dismantled.

The green house (GH) which was temporary structure for preventing spread of contaminants during dismantling activities was installed around the unloaded rotary kiln. The GH was built by attaching plastic sheets to pipe frames by using adhesive tapes. The size of the GH was 11.0 x 7.0 x 4.0m.

Next, the intermediate receiver and the screw feeder were dismantled. After collection of UF4 powder form inside of the rotary kiln, the rotary kiln was cut by a mechanical cutting. The crusher and the bag filter were dismantled. After finishing dismantling activities, the GH was removed.

Cut pieces were stored into 1M3 mesh containers. Workers wore cotton gloves and rubber gloves during dismantling activities outside of the GH and wore cotton gloves, double rubber gloves, tyvek protective clothing, full-face mask during dismantling activities in the GH.

Total weight of equipment and total manpower of workers were 14,942kg (without pipes, valves, cables), 1,544.6man-hours respectively in JAEA.

Dismantling Procedure of Rotary Kiln in KAERI

The hydro fluorination rotary kiln was installed in the kiln room on 2nd floor of UCP.

Pipes, cables, and ducts connected to stirred bed reactor

which installed near west side wall in the kiln room were cut down about 40cm long by using a cable cutter, a nibbler or a pipe cutter for decontamination after moving to the specified working place. When pipes with asbestos were removed, workers had to wear half-face masks.

The GH was constructed by closing openings of rooms and workshop’s wall with acryl plates or other adequate material. Size of the GH installed for 2nd floor of UCP was 1,560m2.

Extraction screw, driving mechanism, reoxidation drum and settler was removed to the specified working place. After that, movable cover, heating muffles and cover of the rotary kiln was removed to the specified working place. After removing cover of the rotary kiln, insulator was removed from the cover of the rotary kiln with wearing tyvek protective clothing and half-face mask. Discharge lock was separated from screw conveyer. Screw conveyer was cut by a rotary band saw.

Almost equipment was cut down 40cm long for decontamination and melting. The stainless steel waste was decontaminated by a chemical decontaminator with an ultrasonic and a steam cleaner for washing in the specified working space. The carbon steel waste was melted using induction melting furnace in the specified working space.

After finishing removal of equipment, floor, walls and ceiling were decontaminated by using the steam cleaner, a planning machine or the scabbler.

Total weight of equipment in the kiln room was 8,519kg. Total manpower of workers for dismantling equipment in the kiln room was 1,029.0man-hours.

Difference of Dismantling Procedure of Rotary Kiln between URCP in JAEA and UCP in KAERI

Diameter of the rotary kiln of URCP in JAEA was twice of that of UCP in KAERI. Length of the rotary kiln of UCP in KAERI was 1.5 times of that of URCP in JAEA. However, weights of those rotary kilns were almost the same. The rotary kiln of URCP in JAEA was installed on the cradle for the rotary kiln which was 1.7m height from the floor. On the other hand, the rotary kiln of UCP in KAERI was installed in the concrete vase which was 0.5m height from the floor.

It was found that there were differences in dismantling procedure and installation situation of equipment between JAEA and KAERI. For example, the rotary kiln was installed on the floor without the cradle in KAERI. The GH which surrounds all rooms in 2nd floor was installed in KAERI.


Fig. 2. Rotary kiln of UCP in KAERI.

COMPARISON OF MANAGEMENT DATA FOR DISMANTLING OF ROTARY KILN

Management data concerning dismantling of the rotary kiln was collected during dismantling activities and analyzed by using mutual decommissioning engineering systems.

Analysis of Management Data Concerning Dismantling Activities

Total weight of equipment and total manpower of the workers were 14,942kg, 1,544.6man-hours respectively in JAEA. Manpower of preparation, dismantling, cleanup process in JAEA was 426.2, 921.6, 196.8man-hours respectively. Table II shows manpower of dismantling process according to work items in JAEA. Dismantling work efficiency in JAEA was 9.67kg/man-hour.

On the other hand, total weight of equipment and total manpower of workers were 8,519kg, 1,029.0manhours respectively in KAERI. Dismantling work efficiency in KAERI was 8.28kg/man-hour.

In spite of having installed the rotary kiln on the cradle, it was found that dismantling work efficiency of JAEA was higher than that of KAERI. In order to clarify these differences, it will be necessary to analyze in detail dismantling activities in the future.

Table II. Manpower of workers of dismantling process for dismantling of the rotary kiln in JAEA

Work items Weight Manpower (kg) (man-hour)Removal of control panels 270 27.8

Removal of rotary kiln, 6,481 699.0crasher, screw feeder

Removal of gas preheater 130 13.5

Removal of hood for 400 44.1Collected powderRemoval of bag filter, 510 40.5

blower, filter unit

Removal of cradle for 6,204 31.5rotary kiln

Removal of concrete base 947 65.3

Evaluation of Management Data of Dismantling Activities in KAERI by PRODIA Code of JAEA

Management data of dismantling of equipment in the kiln room of KAERI were evaluated by PRODIA code of JAEA. (4), (5)

Dismantling procedure and dismantling method was assumed to be the same as JAEA. Dismantling procedure was assumed as follows.

- Firstly a workshop for dismantling of equipment was examined.

- Floor of the workshop was covered by vinyl sheets.

- After that, cutting devices were set in the workshop.

- Materials and tools were carried into the workshop.

- A GH was installed in the kiln room as shown in Fig.3.

- After finishing the preparation process, equipment was cut and put into 200L drums in the GH.

- 200L drums which stored cut pieces were transported to a storage space.

- The materials, the tools and the cutting devices were carried out from the workshop.

- The GH was removed and the workshop was cleaned.

Total estimated manpower of workers for dismantling of equipment in the kiln room of KAERI was 1,294.8 man-hours by using PRODIA code. It was found that manpower calculated by using PRODIA code was 1.26 times of actual manpower in the kiln room of KAERI in spite of not having included decontamination activities.

RESULTS

JAEA and KAERI started benchmark tests in order to verify mutual decommissioning engineering systems. The rotary kiln was selected as the object of benchmark tests.

It compared about dismantling procedure and management data for dismantling the rotary kiln of JAEA and KAERI. There were differences in dismantling procedure and installation situation of the rotary kiln between JAEA and KAERI. Dismantling work efficiency of JAEA was higher than that of KAERI.

Management data for dismantling the rotary kiln of KAERI was calculated by using PRODIA code of JAEA. Manpower


calculated by using PRODIA code of JAEA was 1.26 times of actual manpower in the kiln room of KAERI.

Fig. 3. The GH for dismantling equipment in the kiln room in KAERI.

REFERENCES

1. S. Ikegami, Y. Tsunashima, M. Murata, et. al., “The current

status of decommissioning on the JAEA's uranium conversion facilities at Ningyo-toge Center,” Journal of the RANDEC (in Japanese), No.39, p18-29 (2009).

2. N. Takahashi, Y. Morimoto, N. Sugitsue, “Decommissioning project of JAEA uranium refining and conversion plant,” Proc. of DD&R 2010, Idaho Falls, ID, August 29 - September 2 (2010) (CD-ROM).

3. D. S. Hwang, K. I. Lee, Y. D. Choi, et. al., “Decommissioning project of uranium conversion plant,” Proc. of DD&R 2010, Idaho Falls, ID, USA, August 29 September 2 (2010) (CD-ROM).

4. H. Usui, S. Izumo, Y. Shibahara, et. al., “Study on evaluation of project management data for decommissioning of uranium refining and conversion plant”, Proc. of WM2012, Phoenix, Arizona, USA, February 26 – March 1 (2012) (CD-ROM).

5. Y. Shibahara, M. Tachibana, M. Izumi, et. al., “Study on applicability of evaluation model of manpower needs for dismantling of equipments in FUGEN -2, preparation and clean-up process in 3rd/4th feedwater heater room”, JAEA-Technology 2011-010 (in Japanese) (2011).

36News

NEWSHighlights of the Month

Company News


NPP News

37 News

HighlightsCNNC Intends to Invest RMB 40 Billion on Construction of Longwan Industrial Plant Nuclear Station in Jiangmen

According to the cooperation agreement signed before the

Qingming Festival between CNNC and Heshan government

under the jurisdiction of Jiangmen city in Guangdong province,

CNNC intends to invest 40 Billion RMB to create a “one-

stop” nuclear fuel processing industrial chain, focusing on the

construction of the uranium purification transformation, uranium

enrichment and nuclear fuel element manufacturing facilities.

The site has been chosen in the Daying industrial plant in

Zhishan town of Heshan city. It is involved in programs of fuel

supply, clean energy construction of nuclear power, energy

structure adjustment and environmental improvement. Both

sides signed two agreements: the investment framework

agreement and the land use agreement of CNNC Longwan

Industrial Plant. According to the agreements, the first-class

international nuclear fuel processing industries will be built

here before 2020, and will gradually become the nuclear fuel

processing and equipment manufacturing center in Asia.

The chairman of CNNC, Sun Qin showed that this program

possesses the advantages of safety, high efficiency and modern

enterprise management mode. It is also a program with intensive

capital, technology, talents and good benefits. It not only serves

nuclear power development on the coastal regions in China, but

also the whole of China, even the globe.

It was learnt that the CNNC has made strict reconnaissance

and quantitative evaluation in almost 40 project alternative

sites in the domestic coastal provinces and cities. The final

determination of the site may be related to the Taishan nuclear

power plant under construction, which is the fourth nuclear

power plant built by CGNPC in Guangdong. According to the

plan, all plants will be put into production in the province by 2020

with coal-saving of 60 million tons a year.

Source : http://www.heneng.net.cn

China Develops the Fourth-Generation Fast Reactor Control Rod

The Fast Reactor is the shortened form of the Fast Neutron

Reactor, which is the fourth-generation nuclear power cause

being researched and developed in China. Dalian Boen Tan

Technology Co., Ltd. and the China Institute of Atomic Energy

jointly realized the autonomic production of the core components

of the control rods.

In 2011, Dalian Boen Tan Technology Co., Ltd. signed the

cooperation agreement with the China Institute of Atomic

Energy, and then they took responsibility for the development

and localization work of the control rods of the fast reactor in

China. During two years, a total of more than RMB 50 million

has been invested into this. Through cooperation with 13

scientific research institutions such as Tsinghua University and

Tianji University, the company has overcome many difficult

problems such as material separation, heat conduction and

expansion.

So far, the company has achieved three national invention

patents in the related field and takes the lead to achieve the

industrialization of boron isotope products in domestic China,

this broke the technology monopoly of a small number of

countries including in Europe and the United States.

The boron isotope products have also been used in fields of

military, PV, LED chip. Sales revenue is expected to reach RMB

30 million in 2013.

Source :http://www.china-nea.cn

Revision of Yangjiang NPP Phase One Ahead of Schedule

On April 10, the drawing revision of the 4LX+3.80 duct and

bracket revision of Yangjiang NPP phase one was completed

and released officially. This achieved the site design subcontract

milestone 431 days ahead of the previous plan. It also created

favorable conditions for the ventilation system installation for the

Yangjiang NPP phases 3 and 4.

38News

Since the professional design work of Yangjiang ventilation

project began, CNNC has continuously optimized the working

process. As the drawings of phases 3 and 4 are similar to

phases 1 and 2, CNNC, positively communicated with the upper

designer, acquiring the updated information of phases 3 and 4,

focused on the change when detailed revision was made and

extensively screened the problems which emerged from phases

1 and 2. Thus, the site changes decreased by about 60% from

the same period compared with phases 1 and 2. This greatly

improves working efficiency, reflects the concept of pursuit of

excellence and fully shows the good image of CNNC.

Source:http://www.heneng.net.cn

Appraisal Kick-Off Meeting of CAP1400 Demonstration Project held in Beijing On April 2, 2013, the appraisal kick-off meeting of the CAP1400

demonstration project (hereinafter referred to as "demonstration

project") was held in Beijing. It is the major special project of

the national large-scale advanced PWR nuclear power plant.

The meeting was organized by the Ministry of Environment

Protection (National Nuclear Safety Administration), and the

deputy director of the NNSA division two, Yu Jun and the vice-

president of the SNPEC, Sun Hanhong and Shi Jialin also

attended the meeting.

At the meet ing, leaders o f the NNSA descr ibed the

arrangements for two review reports of a subsequent CAP1400

demonstration project, PSAR report, experimental verification

and other review work and plans, and also cleared all standards

and requirements for experimental verification under the

PSAR stage. Through a series of strict appraisals with safety

standards, the demonstration project will meet the standard

requirements of the most advanced nuclear power safety laws

and regulations at home and abroad and finally become the

three-generation advanced PWR nuclear power unit on behalf of

the national innovation ability.

About 200 leaders, experts and representatives attended the

meeting, they came from the Nuclear Safety Center of the

Ministry of Environment Protection, Nuclear and Radiation

Safety surveillance of North China, Suzhou Nuclear Safety

Center (including CGNPC Design Institute), Beijing Nuclear

Safety Review Center (including the CNPE), NPIC, SNPTC,

the State Nuclear Power Demonstration Plant Co., Ltd and the

Shanghai Nuclear Engineering Research and Design Institute.

Appraisal kick-off meeting of CAP1400 site

Source : www.heneng.net.cn

Hoisting of High-Temperature Gas-Cooled Reactor Completed

On April 14, the shielding cooling water A module, the high-

temperature gas-cooled reactor charged by China Nuclear

Industry 23 Construction Company was hoisted into place. This

marks that the hoisting of the shielding cooling water to 8 meters

below the high temperature gas cooled reactor evaporator

compartment is completely finished, which creates a good

beginning for the follow-up work of the project.

During this hoisting, both two sets of the module adopt the 156

steel tubes with diameters of 38 mm. They form the tube bundle

of 7310mm x 7200mm x 7320mm through the connecting of the

header below. On April 10, China Nuclear Industry 23 Company

finished the whole manufacturing of two sets of modules; On

April 14, at 6:00am, a 400 ton crane began to hook turn; at

6:45am, the first set of shielding water modules was hoisted in

place; and at 8:30am, the second module finished hoisting.

Source:http://www.heneng.net.cn

Appraisal kick-off meeting of CAP1400 site Source:www.heneng.net.cn


40News

First set of CAP1400 Voltage Regulator Forgings Smelted and Cast

The first domestic manufacturing CAP1400 nuclear power

stabilizer forgings have been smelted and cast in the steelshop

of China National Erzhong Group.

The CAP1400 nuclear power stabilizer forgings adopt the

3rd generation non-active nuclear power unit standards with

independent intellectual property rights. With strict requirements

for the chemical composition control, non-destructive testing

and mechanical property, the CAP1400 nuclear power stabilizer

forgings is currently one of the most difficult smelting products

to be produced. Its smelting process must be thoroughly de-

phosphorised, de-sulfurated, de-gassed and edulcorated to

precisely control the chemical composition and maximize the

ingot purity in order to ensure the product quality.

Erzhong Group made full preparation for the raw material and

production equipment status. During the smelting and casting

processes, the phosphorus content must be strictly controlled

to precisely manage its chemical compositions and to increase

the purity of the molten steel. At the same time, the temperature

and speed injection also need to be carefully controlled.

Through careful preparation, smelting and casting, the smelting

technology parameters such as chemical composition are

ensured to completely conform to the requirements of the

process.

Source:http://www.cnnc.com.cn

China’s First Nuclear Main Pump Motor Developed by Harbin Electric Corporation DeliveredOn April 8, China’s first nuclear main pump motor of Fangjiashan

nuclear power engineering was successfully delivered. It was

developed by the Harbin Electric Corporation with independent

intellectual rights, indicating that China has broken the long-

term technology monopoly of the main pump group created by

Europe, the United States and other countries.

According to the factory testing data, each performance

index of the motor is in complete compliance with the design

requirements and reaches the international advanced level.

Fangjiashan nuclear power engineering is an expansion project

of Qinshan Phase I Nuclear Power Engineering, which plans

to build two units of the PWR nuclear power unit of one million

kW, adopting 2nd generation advanced PWR technology. Harbin

Electric Corporation and Austria Andritz Group jointly won the

bid for a total of six nuclear main pump groups of two units,

among which the motor adopts the shaft seal design developed

by Harbin Electric Corporation.

Source:http://www.china-nea.cn/

China Self-developed 3rd Generation ACP1000 Reaches International Level through Identification

According to a report in economic daily, the preliminary design

of the advanced PWR ACP1000 with complete independent

intellectual property rights passed the authority identification

of the national nuclear industries, which is self-developed by

CNNC. Experts agreed that the technology and safety index

have reached the same level of 3rd generation nuclear power

units abroad and its design and construction can fully achieve

democracy.

It was learnt that ACP1000 was developed on the basis of

CNNC’s more than 30 years of nuclear power research, design,

manufacture, construction and operation experience, which

fully adopts advanced concepts of international 3rd generation

nuclear power technology, draws experience and lessons

from the Fukushima nuclear accident and fully meets the most

advanced regulatory standards in the world. The ACP1000

possesses good autonomation and localization bases of nuclear

power and a rich experience in construction and operation which

has great economic advantages.

Source：http://www.heneng.net.cn

TWBB Won the Bid for the First Nuclear Power Project in Western China

The Baoding Tianwei Baobian Electric Company (TWBB) won

the bid for 7 single phase booster main standby transformers

of 400MVA/500kV used to support the units of 2×1000MW in

Fangchenggang NPP Phase 1 project, the first commercial

heavy water reactor nuclear power station in China.

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Fangchenggang NPP is the first nuclear power project which

starts to be constructed in China’s western region and ethnic

minority areas. Two pressurized water reactor nuclear power

units with capacities of 1.08 million kW each are to be built in the

first phase and the first unit is planned to be put into commercial

operation in 2015.

Source：http://www.heneng.net.cn

L-3 MAPPS Full Scope Simulator for Embalse Is Ready for Training

MONTREAL, April 25, 2013 – L-3 MAPPS announced today that

the Embalse full scope simulator it developed for Nucleoeléctrica

Argentina S.A. (NA-SA) was put into service on March 22, 2013

at the Embalse nuclear power station on the southern shore

of a reservoir on the Rio Tercero, near the city of Embalse in

Córdoba Province, Argentina. L-3 MAPPS and NA-SA gathered

in Córdoba today to celebrate this significant success, a project

milestone known as “Ready for Training.”

The simulator will support enhanced operator training for the

single unit at the Embalse site – a CANDU 6 pressurized

heavy water reactor with a net output of 600 MWe, which

went into commercial operation on January 20, 1984. The

last full scope CANDU plant simulator L-3 MAPPS developed

was for the Qinshan Phase III plant in Zhejiang, China, which

entered service in the first quarter of 2003. Since then, L-3

MAPPS has introduced significant technology inroads that the

industry has adopted, including plant models developed in L-3’s

Orchid®simulation environment, emulation of redundant plant

computer systems and highly advanced compact input/output

systems, all of which have been applied to making the Embalse

simulator completely state-of-the-art.

“Through this development effort, L-3 has produced the most modern full scope CANDU plant simulator using today’s very latest hardware and software technologies and simulation techniques,” said Michael Chatlani, vice president of marketing & sales for L-3 MAPPS Power Systems and Simulation. “This is an important project for L-3 MAPPS as it makes us uniquely qualified to build the next generation of CANDU plant simulators. We are very grateful to NA-SA for giving us the opportunity to advance our solution to this stage.”

“With the Embalse full scope simulator in service, the first

major deliverable for the plant’s life extension project has been successfully achieved,” said Rubén Semmoloni, Embalse NPP life extension project director for NA-SA. “We applaud the L-3 MAPPS and NA-SA technical teams for their teamwork and dedication in delivering the simulator, which will be a central part of our personnel training and safety culture for the next 25 years.”

The Embalse full scope simulator features L-3’s leading Orchid

simulation environment running on a PC/Windows platform.

All of the plant’s simulated operational systems are developed,

validated and maintained within Orchid, including the reactor,

nuclear steam supply systems, balance of plant systems,

electrical systems and I&C systems. The plant computer

systems, known as Digital Control Computers (DCCs), are

represented with a fully emulated dual DCC that is integrated in

the full scope simulator.

Source：www.L-3com.com/MAPPS

Company News

CNNC and SINOPEC Establish a Joint Venture to Expedite Exploration for Uranium ResourcesOn March 29, the Department of Geology and & Mining CNNC signed an agreement with China Petroleum & Chemical Corp. (Sinopec) to set up the joint venture of “CNNC and SINOPEC Uranium Resources Co,.Ltd”, which is a specific implementation of the strategic cooperation agreement between the two groups. It also marks the cooperation of the two groups in the field of uranium resources exploration, and development will enter a significant stage. Du Yunbin, the director of the Department of Geology and & Mining CNNC, and Zhou Liqing, the general director of Sinopec, signed the agreement.

The “CNNC and SINOPEC Uranium Resources Co,. Ltd” is treated as the cooperation platform for the two government-owned companies to accelerate the exploration of uranium resources. Taking the Chaideng area of Inner Mongolia as the breakthrough point, the two groups will play their respective

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Qian Zhimin said during the ceremony: “This program involves nuclear fuel supply, nuclear power clean energy construction, energy structure adjustment and environmental improvement. To realize this program is actually making a contribution to the construction of “beautiful China”. CNNC and its nuclear fuel company will conscientiously implement the related requirements of the board of directors, move the work forward step by step and complete it as soon as possible in accordance with the international standards.”

Liu Hai said in his speech that Heshan will fully implement all the preparation work for this program; and will give logistical support with full effort after completion. He hopes that both sides can work together according to the goal and finally realize the task after the agreement was signed.

CNNC has attached great importance to the construction of the nuclear fuel industry. In February 2012, the planning and construction scheme was reviewed and adopted by CNNC and the leading and working groups were set up by the leaders of CNNC themselves. The group made strict reconnaissance and quantitative evaluation towards nearly 40 alternative project sites in the domestic coastal provinces and cities. According to the preferential principle of planning and site selection, the Daying industrial park at Zhishan town in Heshan and Jiangmen city, Guangdong province has finally been chosen for construction of the Longwan Industrial Park.

Source：http://www.china-nea.cn

Shandong Taihai Group Buy out France Nuclear Power Enterprises.Laishan nuclear power equipment industrial park added a new member: the titanium alloy project, invested by the Calvi Group in Italy with a total investment of €50 million, has started planning and constructing the park. Well over 20 nuclear-

advantages to gradually expand the areas of collaboration and scope in order to achieve a cooperation model.

Source：http://news.bjx.com.cn

CNNC Invests to Constructing a “One-Stop” Nuclear Fuel Processing Industrial ChainOn March 31, the cooperation agreement signing ceremony of CNNC Longwan Industrial Park took place in Beijing. CNNC and Heshan city in Guangdong province jointly signed the investment framework agreement and the land use agreement. According to the national nuclear power development plan and CNNC’s nuclear fuel industry development strategy, CNNC will invest in constructing the park in Jiangmen, Guangdong province, to create a “one-stop” nuclear fuel processing industrial chain and to construct facilities of uranium purification transformation, uranium enrichment and nuclear fuel component manufacturing.

According to the plan, the international first-class nuclear fuel processing industry cluster will be built before 2020 with the processing management operation system of “cooperation and win-win” and will gradually become a symbolic nuclear fuel processing center in Asia. These are the major initiatives of CNNC: to focus on the domestic and international nuclear power development, to optimize allocation of resources, to enhance the core competitiveness of industry development, and to realize the transformation, upgrading and fast development of the nuclear industry. It is also significant for the development of China’s nuclear power and nuclear fuel industries.

Also attending the ceremony were: the Chairman, Party Secretary of CNNC, Sun Qin; the General Manager and Deputy Party Secretary, Qian Zhimin; the Deputy General Manager and member of Party Commission, Yang Changli; Deputy Director of the State of Science, Technology, and Industry for National Defense; Jiangmen Municipal Party Secretary, Liuhai and Deputy Mayor, Wu Guojie; Heshan Municipal Party Secretary, Guo Wei; the General Manager Assistant of the CGNPC, Liu Kaixin.

Sun Qin said at the symposium before the ceremony: “With the features of safe, efficient and modern enterprise management mode, Longwan Industrial Park can not only serve China’s coastal regions, but also the whole of China and the world. As a program of the fund, technology, talents and benefit intensiveness, great support could be given by the Jiangmen Municipal Party Committee and the Municipal Government. Social risk assessment and science popularization will be carried out properly.”

Signing Ceremony of CNNC Longwan Industrial Park Source:CNEA

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related enterprises have been established here, a park lead by the nuclear power equipment manufacturing enterprise, Taihai Group.

Laishan district’s restructuring supports leading enterprises to make use of the opportunities brought by the financial crisis – bringing lower costs than Europe and America to advanced enterprises.

Ta iha i Group is a pr iva te nuc lear power equ ipment manufacturing enterprise in Laishan district; the group’s development has been very rapid since its establishment. In recent years, many European nuclear power enterprises have encountered management problems owing to the financial crisis, which have brought opportunities for low-cost M&A. Taihai Group seized this opportunity and purchased eight enterprises from a world-class nuclear power equipment manufacturer, the Manoir Industries, in 2012 – with the support of the district committee and government. Thus, at a single stroke Taihai Group has become the world’s only nuclear power equipment manufacturer of the three and a half generation. It is also the only domestic nuclear power equipment manufacturing enterprise with permission of the European Union at the moment – this gives it a large share in the global market for the specialized equipment of nuclear power piping.

Laishan district has constructed a nuclear power industrial park of 7 square kilometers, lead by the Taihai Group. The park has attracted many of the world’s famous enterprises such as the Calvi Group in Italy and has formed a complete industry cluster by means of canvassing business connected with the products of titanium alloy materials, air cooling and dust purification which is required for nuclear power equipment production. Such enterprises not only serve for Taihai Group, but also expand the business both domestically and overseas. Thus, Laishan has broken with convention and built a new industry by one overseas merger and acquisition.

It is expected that the operation revenue of Taihai Group will reach ten billion RMB in three or five years, this will help drive the company. Currently, under the impetus of the nuclear power equipment manufacturing industries, the industrial structure of Laishan district is moving forward to the features of “export-oriented, high-tech, emerging industry and green”.

The secretary of Laishan district committee, Jin Zhihai attaches great value to the advantages brought by the overseas M & A. He said that the advantages of Laishan district are a good industrial development foundation; the capability of overseas M & A and that many large and high-level enterprises are based there. In the future, Laishan district will positively replicate its experience of the nuclear power equipment industry to use in the industries of oil equipment, biomedical, energy conservation

and environmental protection, and push the enterprises with strength to make M & A by “going out” in order to enhance the level of enterprises and industrial structure of the whole district.

Source：http://www.china-nea.cn

China’s Independent R & D of Nuclear Power Plant DCS System put into OperationNingde NPP Unit One in Fujian province has been officially put into operation. It is the first million-kilowatt NPP unit to adopt the DCS system of HOLLIAS-N, this means that the independent R & D nuclear power plant DCS system developed by Beijing HellySys Automation Technologies has also gone been put into use officially. It also breaks the industry monopoly of the internationally renowned DCS manufacturers on the nuclear power control field in China.

I t has been learnt f rom Bei j ing Hel lySys Automat ion Technologies that the DCS system of HOLLIAS-N which they developed, is a high-end DCS system and non- security DCS products targeting NPP units of one million kilowatts. Since the R&D of this system began in 2006, seven years has already passed, and the system has been applied in many nuclear power projects such as Hongyanhe, Ningde, Yangjiang and Fangchenggang.

Source:http://www.china-nea.cn

CNNC Nuclear Power Corporation and China CNNC Baoyuan Property Holding Corporation Starts Strategic Cooperation on Nuclear Energy ServicesOn April 15, the CNNC Nuclear Power Corporation and China CNNC Baoyuan Property Holding Corporation signed a strategic cooperation framework agreement on nuclear service, aiming to further promote the professional nuclear power operation of CNNC, reducing operating costs and enhancing the core competitiveness of its nuclear industry service. The signing of this agreement marks the official start of the strategic cooperation between the two corporations. Both sides will be based on the overall strategic nuclear group to establish a long-term strategic cooperative partnership with the purpose of “complementary advantages, common development, mutual benefit and win-win cooperation” through innovation and promotion of the business model. The Party member and Deputy General Manager of CNNC, Qiu Jiangang and the General Manager of the CNNC Nuclear Power Corporation, Chen Hua attended the signing ceremony.

Before the signing ceremony of the seminar, Qiu Jiangang said that this signed contract is of great significance for the beginning

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of the nuclear industry service and it is an important to improve the service further. He hopes that a qualified multi-level service platform could be able to be established to provide high-quality service, at the same time; he also hopes to get support and help from the CNNC Nuclear Power Corporation. Chen Hua hopes that the business level could get improved and costs be controlled through this cooperation.

According to the content of the agreement, the two corporations will jointly promote the application of technical support services in the field of the nuclear power operation industry. Both sides will set up a promoting working group and regularly organize docking communication meetings to guide and coordinate the respective member units to promote nuclear industry service.

Source: http://www.heneng.net.cn

Ningde NPP Unit One Comes into Commercial Operation FormallyOn April 15, unit one (1.089 million kW) of Fujian Ningde Nuclear Power Corporation, invested by Datang International Power Generation Corporation, completed its full load trial operation for 168 hours and formally came into commercial operation.

The planned total installed capacity of Ningde NPP project is six units with total one million kilowatts, and four units of one million kilowatts which are under construction in the first phase. The equity ratio of Ningde Nuclear Power Corporation accounts for 44% of the shareholding of Datang International Power Generation Corporation. GNIC owns 46% shares and Fujian Energy Group hold 10% of Ningde Nuclear Power Corporation.

Datang International Power Generation Corporation announced that Ningde unit one is the key milestone of the company in the field of nuclear power. Ningde NPP lies in the first island chain and is the domestic million-kilowatt unit with the highest localization rate. The successive production of Ningde NPP cannot only bring a stable profit to the company and promote its sustainable development, but also play an important role in optimizing the company’s power structure and environmental protection.

Source：http://np.chinapower.com.cn

ZZSS Obtained the First Civil Nuclear Safety Equipment Manufacturing CertificateZhejiang Zhongda Special Steel Company (hereinafter referred to as ZZSS) has received its Civil Nuclear Safety Equipment Manufacturing Certificate issued by the National Nuclear Security Administration (NNSA) and become the first nuclear

associated enterprise to receive this license in Jiaxing, Zhejiang province.

The company mainly produces boilers and stainless steel seamless tubes used for heat exchangers in addition to other products. In 1998, ZZSS received the certificate of “qualified suppliers of non-safety stainless steel pipes”. In August 2010, the company submitted its application for the civil nuclear safety equipment manufacturing license to the NNSA. After many rectification tests, ZZSS finally received the NNSA’s recognition in aspects of quality assurance ability, staffing, facilities and technical reserves. The company is considered to have the abilities required by Article 13 of the Regulations on Supervision and Management of Civil Nuclear Safety Equipment and Article 8 of the HAF601 in the field of civil nuclear safety equipment manufacturing.


Liuzhou OVM Steps to the 3rd Generation Nuclear PowerThe type test for the CP1000 nuclear-oriented pre-stress anchoring system developed for the 3rd generation nuclear power took place at Liuzhou OVM Machinery Corporation (hereinafter referred to as OVM) at the end of March to early April 2013. It was seen by relevant people from three well-known domestic steel wire companies, leaders and experts of the CNPE and people of the National Construction Engineering Quality Supervision and Inspection Center gathered in Liuzhou. The test results showed that all performances of this system met the requirements of relevant standards. The success of this test laid a solid foundation for products of OVM to step to the 3rd generation of nuclear power.

In March 2008, after years of effort, OVM finally entered the field of nuclear power. Equipment such as the K series of anchorage and relevant stretch-drawing and pipe forming developed by the company have been successfully applied on seven nuclear power projects which adopt the 2nd generation advanced technology. After Japan’s Fukushima nuclear accident in 2011, every country attached greater importance to the safety of the nuclear power. The accreditation in China was restarted in October 2012 after stopping for more than one year. It requires newly-built nuclear power projects to adopt the 3rd generation technology.

The 3rd generation technology is significantly different from the 2nd generation. At present, Tianwan NPP, Sanmen NPP and Taishan NPP are adopting the 3rd generation technology and those technologies originate in different countries: Tianwan NPP

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uses Russian technology, Sanmen NPP uses American and Taishan NPP has French. The American 3rd generation nuclear power technology doesn’t use pre-stressed concrete, while the Russia and French ones do and all use anchorage devices with 55 holes.

As a major nuclear power country, China has been actively developing its own 3rd generation nuclear power technology. The 3rd generation ACP1000 technology has passed all sorts of reviews and designs and is intended to be used for the first time in Fuqing NPP phase III at the end of 2013. After many modifications, anchorage devices adopted by ACP1000, the type with 55 holes was finally utilized. The CP1000 nuclear-oriented pre-stress anchoring system developed by Liuzhou OVM Machinery Corporation was developed for the ACP1000; meanwhile, it also meets the 3rd generation operating requirements of Russia and France. During the developing process, it received great support and help from CNPE.

The ACP1000, as a technology with independent intellectual property rights, will be a vigorously promoted technology used in the future and the main technology for nuclear export in China. At present, countries such as Pakistan and Argentina intend to introduce this technology.


A 200-ton “Forming Machine of Difficult Forming Parts” to be Used for Nuclear PowerOn Apri l 18, at the 10th Ningbo Fasteners, Parts and Manufacturing Exhibition, an eye-catching machine with the intention to compete with world-class ones can “eat” steel and then “spit” screws at the same time. It can product 280 screws per minute, while the most advanced German machines can only make 240. All attendees were curious of it and anticipate the “Chinese speed” in the fastener field.

Five years ago, Ningbo Si Jin Machinery Company with “China Speed” was only a supporting enterprise with no independent products, but it has generated great energy in a short time after the transformation and upgrading of its technological innovation. In May, a “forming machine of difficult forming parts” of about 200 tons will be produced. Screws created by the machine will be used on planes, high-speed rails and nuclear power equipment.

Si Jin Machinery Company was founded in 1995 in Ningbo national hi-tech zone of intensive high-tech enterprises. The company’s founder and chairman, Li Zhongming said that the “Si”

CNOC Gains Experience from US Nuclear Power Industries

Su Shengbing, the General Manager of the operational

department of the CGNPC and the CNOC, visited the INPO,

EPRI and EXELON together with his fellow staff members,

aiming to broaden the external technical support and experience

feedback approach. The two sides had a thorough exchange

regarding the direction and field of future cooperation.

In the Charlotte Center of the EPRI, Su Shengbing, representing

in the company name comes from a character of his daughter’s name, and “Si Jin” means to further develop and move forward.

During more than ten years, the company had been making accessories for a well-known Ningbo plastic machinery company but its company production never broke through RMB 50 million.

In 2006, the 45-year old Li Zhongming considered the enterprise transformation and decided to produce “cold header” - a machine used to produce various kinds of standard parts, fasteners and special-shaped pieces. Steel, without heating, can be put directly into the cold heater, then screws and bolts will be “spat” from it.

Li Zhongming said it was his sincerity that impressed the scientific research, its strength coming from the Ningbo high-tech zone management committee as he tried to satisfy all the R&D requirements cited by them.

In 2008, in one swoop Mr. Li eliminated more than 50 sets of equipment with inefficiency, low machining precision and quality, and then purchased a new CNC machine. More than RMB 20 million was invested in the technical innovation in this year.

At the beginning of 2012, Si Jin combined with Zhejiang University and Shanghai Jiaotong University to conduct research of the “forming machine of the difficult forming parts”.


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Yang Jiechi attended the meeting and delivered speeches. Wu

Xinxiong, Deputy Director of the National Development and

Reform Commission and Director General of National Energy

Administration, Zhang Guobao, President of the Overseas

Association; Zhai Juan, Deputy Foreign Minister; Wang Chao,

Vice Minister of the Ministry of Commerce; Luo Jiahui, the

American Ambassador to China; Zak, Director of the U.S. Trade

and Development Agency also attended the meeting. Chairman

of the State Nuclear Power Technology Corporation (SNPTC),

Wang Binghua, presented at the meeting and delivered a speech

on the “development of clean energy industry and Sino-US

bilateral cooperation dialogue”.

Mr. Wang introduced the progress of the largest cooperation project of energy technology between the two countries at present, the world’s first four AP1000 units. This is a self-reliance supporting a 3rd generation nuclear power project in China. He said that the two countries have walked in the forefront of the world on the 3rd generation nuclear power technology’s innovation and application. During this process, the two countries formed a profound cooperation basis and long-term cooperation intention.

Mr. Wang shared his own contemplation towards deepening the bilateral nuclear power cooperation from the point of view of enterprises. He pointed out that nuclear power enterprises of the two countries have carried out practical cooperation or reached a consensus on the cooperation on the aspects of providing mutual technical advice and support, jointly developing new reactors, building a global supply chain, promoting industry standards, jointly developing the international market, international investments and mutual strategic investments, taking AP1000 construction projects as the starting point. Ongoing current and future cooperation will help enterprises to accelerate technology innovation and improve the competitiveness of the nuclear power market, including in China and the United States.

He hopes that the two countries will provide more policy support towards high technology control, outbound investment approval, developing the third party market, strengthening nuclear safety regulations, industry certification and ensuring the fuel supply; as well as set up further effective communication and consultation mechanisms between the government and enterprises in order to benefit mankind in using safer, greener and more economic nuclear power.


the CNOC and EPRI of the CGNPC, signed the member

agreement, which means that the technical achievements and

experience of NMAC can be shared together among various

nuclear power base and business centers affiliated to the

CGNPC and the maintenance skills and technology level of the

equipment improved.


General Manager Gu Jun Meets with Senior Delegation Group of Swiss ElectricityOn April 9, 2013, the president of the ALPLQ, Mr. Hans

Schweickardt together with his senior delegation group visited

the SNPTC. The General Manager of SNPTC, Gu Jun, Deputy

Director of the expert committee, Sun Changji and the CIO, Guo

Hongbo met with them.

The SNPTC introduced its company profile and the current

situation of their own programs of third-generation nuclear

power and the national large-scale advanced PWR CAP1400.

Both parties recognized that the development of nuclear power

is the best choice to solve the problems of energy demand and

carbon dioxide emission reduction in the future.

Members of this senior delegation group are coming from the

power enterprises from Switzerland and Europe (including the

ALPIQ, AXPO, BKW/FMB, the Swiss federation of the electricity

utilities and the ETHZ). They are aiming at researching the

current situation of nuclear power in China, especially the

research, construction and future development of the advanced

reactor.


President Wang Binghua Discussed Nuclear Energy Cooperation between China and the USOn April 13, the 'Sino-US energy cooperation dialogue'

kicked off in Beijing. It was jointly held by the China Industry

Overseas Development and Planning Association (hereinafter

referred as Overseas Association) and the Sino-US Energy

Cooperation Program (hereinafter referred to “ECP”). The US

Secretary of State, John Kerry and Chinese State Councilor,

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Deputy Director of GACC Meets with Director of NNSA under DOE

On April 16, Lu Peijun, Deputy Director of GACC (China General

Administration of Customs) met with Ms. Harrington, Director

of NNSA (National Nuclear Security Administration) under

DOE (US Department of Energy). Both sides made positive

comments on the cooperation results of GACC and DOE and

exchanged views on issues such as export control cooperation,

participating in the 2014 nuclear security summit, continuing to

hold the tripartite expert seminar of China, the United States and

Russia.

Mr Lu put forward three suggestions on further deepening the

cooperation between the two countries: firstly, continuously

strengthening the cooperation of the “megaports initiative

pilot project”, broaden and enrich the cooperation content and

improve efficiency; secondly, steadily push forward all works

on China’s customs radiation detection training center project

(jointly built by China and the US); thirdly, speed up the setting

up of a new memorandum of understanding on preventing the

illegal trafficking of nuclear materials and other radioactive

substances.


PFCE Inspects Taishan to Look for Nuclear Power PartnersOn April 11, members of PFCE visited Taishan and inspected

the investment environment in order to seek further cooperation

development.

On April 12, they visited the Winners Group and listened to

its company profile and product introduction. Afterwards, they

went to the Industrial New City to get an understanding of the

construction progress of Anshibei Nuclear Power Equipment

Co., Ltd invested by a French enterprise.

At the subsequent communication meeting, staff of the Industrial

New City introduced the plan and prospects of the park to the

members of PECE. It was learnt that this newly-built industrial

park is a major industrial transfer park in Guangdong province

which belongs to the fixed-point industrial park of the province

and promotes the development of nuclear power equipment.

Also, the cooperation framework agreement with CGNPG was

signed. There has a platform for detecting, scientific research

and innovation coming from the national machinery and

equipment testing laboratory there.

After an inspection, PFCE said that they are looking for the

nuclear power equipment partners and they are very interested

in the laboratory testing project, hoping to further strengthen

communication and cooperation. Meanwhile, they also asked

questions on issues such as park investment environment and

factory matching and got the corresponding solutions. Zhang

Lei, Mayor of Taishan attended the welcome meeting that night

and said he hoped that French firms could take root in Taishan.


President of CNNC, Sun Qin, Meets with Vice-General Manager of Russian National Atomic Energy CorporationOn April 22, the President of CNNC, Sun Qin, met with the

Vice-General Manager of the Russian National Atomic Energy

Corporation, Komarov. Mr Sun introduced the current situation

of the Tianwan NPP Phase II which is co-constructed by both

sides, and reaffirmed the position of the strategic cooperation

partnership between CNNC and the Russian National Atomic

Energy Corporation. Komorov conveyed the regards of Sergei

Kiriyenko, General Manager to Sun Qin and showed that they

are willing to develop bilateral comprehensive cooperation in the

field of nuclear energy on the basis of mutual benefit and win-

win results.

Both sides are satisfied with China and Russia’s cooperation

in the field of nuclear energy and are full of confidence in

expanding and deepening cooperation in the future. The Vice-

General Manager of CNNC, Yu Peigen and Russian embassy

officials attended the meeting.

Source: http://np.chinapower.com.cn

CNNC Exchanged and Cooperated with Argentina Nuclear Power GroupOn April 22, Lv Huaxiang, Vice-General Manager of CNNC and

R.Quintana, President of Argentina Nuclear Power Group co-

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chaired the high-level nuclear cooperation meeting for the first

time. Both sides made candid and friendly exchanging towards

concerned issues and formed a consensus on related contents.

Both sides hold a positive attitude towards future nuclear power

cooperation. On the same day, Mr Lv also attended the meeting

activities held by the director of Nuclear Power Department

of the National Energy Administration, He Weiping and the

delegation of Argentina Nuclear power Group.

Source: http://www.china-nea.cn

Biggest Overseas Investment Project of CGNPC Starts Mining Uranium in Africa

The Namibia Husab Uranium Mine Project of CGNPC has

begun construction, this is the largest cooperation project

between China and Namibia. After it is put into production, the

exports and GDP of Namibia will grow 20% and 5% respectively.

This product is the biggest China-invested mining project in Africa at present. It is one of the major discoveries in uranium resources exploration in Africa and even the world during the last ten years, and its uranium resources have ranked the third in the world. After going into production, it will become the second largest uranium mine in the world and its total production quantity will meet the natural uranium demand of 20 nuclear power units of a million kilowatts for nearly 40 years.


L-3 MAPPS to Introduce MAAP5 Severe Accident Simulation on Ling Ao Phase II SimulatorMONTREAL, May 6, 2013 – L-3 MAPPS announced today that it has won an upgrade contract from Daya Bay Nuclear Power Operations and Management Co., Ltd. (DNMC) to

equip the Ling Ao Phase II full scope simulator with a severe

accident simulation model to enhance training scenarios that

simulate degraded reactor core conditions. The project, which

underscores L-3 MAPPS’ continued commitment to DNMC,

will commence immediately and is slated to be in service at the

beginning of 2014.

“Since the Fukushima accident in 2011, we have seen increased demand for severe accident simulation on real-time nuclear plant training simulators,” said Michael Chatlani, vice president of marketing & sales for L-3 MAPPS Power Systems and Simulation. “This upgrade project is important to L-3 MAPPS as it will allow us to field exciting new simulation products and solutions in the near term and to once again provide DNMC with a successful solution.”

L-3 MAPPS will connect the Electric Power Research Institute’s (EPRI) Modular Accident Analysis Program (MAAP5) to the Ling Ao Phase II simulator. MAAP5 is a software program that performs severe accident analysis for nuclear power plants, including assessments of core damage and radiological transport.* The simulator will also be equipped with new 2-D and 3-D animated, interactive visualizations of the reactor vessel, containment building and spent fuel pool to provide operators with additional insight into the behavior of theplant during severe accidents. The 2-D graphics will be enabled with L-3’s Orchid® Control System and 3-D visuals will be powered by Bridgeworks© from TriLink Systems.

In addition to the normal operations and abnormal, off-normal and emergency event training for which the simulator is currently extensively used, the upgraded Ling Ao Phase II simulator will be used for training scenarios relating to degraded reactor core conditions that result in fuel melting, including cladding oxidation and hydrogen generation, vessel failure, containment failure and fission product release.

The Ling Ao Phase II nuclear plant, owned by Ling Dong Nuclear Power Company, comprises the first two CPR1000 nuclear generating units that were put into commercial operation – the first unit in September 2010 and the second in August 2011. The CPR1000 is a Chinese standard design featuring a

1,080-megawatt (MWe) three-loop pressurized water reactor

(PWR). The Ling Ao Phase II full scope simulator, built by L-3

MAPPS in cooperation with AREVA and Siemens, was put into

service in August 2009.

Source: www.L-3com.com/MAPPS

High-level nuclear cooperation meeting between CNNC and Argentina Nuclear Power Group Source:www.cnnc.com.cn

49 News

50News

NPP News Primary Loop System of Sanmen Unit One Finished Welding The welding was completed on Sanmen unit one’s primary loop system on April 7. The first AP1000 nuclear power plant in the world completed 100% thickness of all entity welding of the main coolant pipe (hereinafter referred to as the main pipe), relying on their own projects Sanmen Nuclear Power Plant Unit 1 of the three-generation nuclear power in China. A total of 6 sections of the main pipes A and B connect the reactor pressure vessel, steam generator and reactor coolant pump to form one closed loop, marking that the primary loop system welding is completed.

Sanmen unit one officially started the main pipe construction last October and the whole process lasted 6 months. The welding used advanced techniques to ensure its quality and efficiency - including laser tracking, 3D modeling, precise CNC groove processing, narrow gap automatic welding and laser tracking measurement of welding contraction deformation.


Fuqing NPP Units 1-6 Pressure-Tight Test CompletedOn April 3, Fuqing NPP Units 1-6 completed their 500kV pressure-tight test of the GIS ultra-high voltage switching station, their full voltage test of the voltage transformer/lightning arrester, and PT metering winding angel contrast test. These were important steps towards the completion of the 500kV sending node in the middle of April.

GIS belongs to the closed gas insulated switchgear and the

aim of AC voltage withstand test is to check the insulation performance. The equipment may have suffered insulation damage during the processes of transportation, insulation and commissioning. An insulation defect could cause different degrees of internal partial discharge, and a long-term discharge could exacerbate the insulation deterioration or even lead to a breakdown or flashover. Early detection of internal partial discharge phenomena is a vital to the improvement of GIS reliability.

The GIS is the public system for unit 1-6, adopting 3/2 connection mode and six series of one-time completion. With a large-scale station, tight schedules and high requirements, this is the first domestic nuclear power project to be constructed. The station can accommodate six units of a million kilowatts each to deliver a full power generating capacity to the grid. It has been put into operation upon completion. Meanwhile it has to meet the power demands of the process system debugging of unit one. Large scale of it leads to an increase in the device’s capacitance. In accordance with the requirements of the 18 major anti-accident measures of the State Power Grid Corporation, the pressure rating level of the scene should reach 90% of the factory pressure-tight standard (previously 80%), which means that the phase voltage should reach 666kV. The requirements of Fujian power grid are stricter; therefore all circuit breakers need to take the fracture pressure test. After various communications, Fuqing debugging group finally decided the test would be conducted according to different regions and phases, and needs to be pressurized 30 times in total. Following that, the PT/MOA full voltage test and the PT angle contrast test needs to be pressurized 36 times, this means that they have to repeatedly verify whether the state and pressure of the 57 breakers, 150 disconnecting switches and 351 SFR air chambers meet each testing requirement. The test began on March 13, and through working overtime and overcoming delays caused by rain, the test was successfully completed on April 3.

Source: http://www.cnpe.cc

First Heavy Equipment of Ningde NPP Unit 3 Hoisted into PlaceOn April 9, the main loop of the first heavy equipment of Ningde NPP Unit 3, voltage stabilizer has been hoisted into place smoothly. This marks the completion of the ABN3EM2-007 which is the key milestone of Unit 3, and a successful start to the installation of the primary loop of heavy equipment.

The voltage stabilizer of Ningde NPP United 3 is about 13 meters high, 2.5 meters in diameter and has a total weight of about 85 tons. It was shipped to 20 meters platform on April 3, and started its hooking turn on April 9 and was finally successfully hoisted into place after more than two hours.

Source: http://www.cni23.com

Diagrammatic figure of AP1000 primary loop system Source:SNPEC

51 News

officially put into commercial operation after being qualified by Fujian Electric Power Company. This was also the first unit to be put into operation after restarting domestic nuclear power. The clean power has begun being constantly supplied into Fujian’s power grid. According to measurement, the daily output of this unit is about 24 million degrees, which can meet the electricity demand of 2.4 million families living in the surrounding area. With the unit connecting to the grid, the clean energy proportion in Fujian province will increase from the current 42.56% to 42.32%. After the completion of the four units of phases one, the annual energy output will amount to 18% of the power consumption in Fujian Province - a substantial increase in clean energy.

Ningde NPP phase one adopts its independent brand of CPR1000 million kilowatt pressurized water reactors and boasts of four nuclear power units with each unit having a capacity of 1.089 million kilowatts. The unit one was put into operation today having poured the FCD on February 18, 2008. It connected to the grid for the first time on December 28, 2012. Through testing of each power platform and minor repair, the various performance indicators meet the design standard.

The Ningde NPP phase one project was invested, constructed and operated by Ningde Nuclear Power Company which was jointly set up by CGNPG, China Datang Group and Fujian Energy Group. Its construction and management was contracted by CGNPC, and its engineering design, equipment manufacturing, engineering construction and technical services were mainly undertaken by domestic enterprises. The integrated localization rate of units one and two will exceed 75%, and one of the units three and four will reach 85%.

After Japan’s Fukushima nuclear accident, according to the conclusion of the national civilian nuclear facilities safety check, Ningde phase one took the lead in completing the safety improvement implementation work among the domestic nuclear power projects under construction. This further improved the unit’s ability to respond to an extreme disaster superposition and security level.

The annual energy output will reach about 30 billion tons after the completion, which can reduce standard coal consumption by about 9.8 million tons, carbon dioxide emissions by about 24 million tons, Nox by about 150,000 tons compared to a coal-fired power plant of the same size. If the coal is transported by train, and one car of the train loads 50 tons and one train contains 50 cars, 11 trains have to be provided to ensure the power supply for 365 days per year.

The construction of Ningde NPP Unit one will play an important role in alleviating electric power and energy transport pressure in the southeast coastal area. It will optimize the energy and

Cold Test of Yangjiang NPP Unit One Completed On March 31, a program of CGNPG, the cold test of Yangjiang NPP unit one was completed as the first loop pressure was dropped to atmospheric pressure and the regulator valve opened.

The cold test was carefully prepared and since its beginning on March 25, the staff ensured the whole process went smoothly. The calculated results of the air content, leakage rate and other key indicators of the first loop were indicated accurately. The results of the cold test of Yangjiang NPP unit one’s main loop met the requirements after the joint inspection of each unit and the scene confirmation by the South Nuclear Radiation Safety Surveillance.

Yangjiang NPP lies in Shahuan of Dongping town, Yangjiang, Guangdong province and plans to construct six PWR nuclear power units of six million kilowatts. This is the second nuclear power base built by the CGNPC in Guangdong province. At present, units one, two, three and four are under construction with unit one scheduled to be completed and put into commercial operation in 2013.


ACME Test System Enters Cold Commissioning PhaseOn March 31, 2013, the non-active reactor core cooling system test facility (hereafter referred to as “ACME”) , which is the major special CAP1400 advanced pressurized water reactor nuclear power plants in China, completed the primary loop hydraulic pressure test over a day and a half.

The ACME test-bed is 1/3 height of the ration test model of the CAP1400, used for validating the performance of the non-active reactor core cooling system and the thermal-hydraulic safety analysis program. It completely simulates the main loop and the non-active system of the prototype plant where the main loop will be undertaking the cold commissioning phase through a hydrostatic test. This marks the end of the construction work of the test bed.

The SNPTC, Shandong Electric Power Engineering Consulting Institute Corporation and the Supervision Company witnessed this test activity.

Source: http://www.snptc.com.cn

Fujian First Ningde NPP Unit One Begins Commercial OperationCGNPG announced that Ningde NPP unit one completed the running test of 168 hours on April 15, 2013 and has been

52News

grid structure, realize the goal to reduce carbon emissions, promoting the construction of an economic zone in channel west bank and ensure the sustainable development of the regional economy, society and environment. It will help construct “beautiful Fujian”.

At present, CGNPG has an installed nuclear power capacity of 7.2 million kilowatts under operation. It has 15 nuclear power units under construction and which will provide a total installed capacity of 17.75 million kilowatts. Safe nuclear power operation achievements are world leading. In 2012, its overall performance ranked in the top ten global industries.


Fangj iashan NPP Uni t One Reaches Milestone of Pressure Vessel Water Flushing

On April 12, the pressure vessel water flushing of Fangjiashan NPP Unit 1 was successfully realized as spurts of water spewed out of the Unit 1 pressure vessel, indicating that the auxiliary system installation work for the nuclear plant has been basically finished and meaning that the commissioning work of the first loop’s nuclear auxiliary system will be conducted gradually.

Pressure vessel water feeding is the joint flushing to several main process systems including the reactor coolant system, reactor safety injection system, chemical and volume control system and residual heat removal system. During the whole process, water is coming from the refueling water tank, and then flushing the related system respectively, water finally went into the pressure vessel. It is also the prerequisite for the joint pressure test of the primary loop system.

The boundary of the Unit 1 pressure vessel water feeding was fully considered by Qinshan NPP and related construction units and the specific schedule of the primary loop flushing and water line plan were released in time in order to ensure this milestone was achieved safely and smoothly.


Conventional Island of Tianwan NPP Unit 3 Formally Started

On April 21, the opening ceremony of the conventional island of Tianwan NPP unit 3 was held in Tianwan NPP site. It was attended by the project owner, the CNNC Jiangsu Nuclear Power Corporation; general contractor, CNPE; the construction unit, Jiangsu Electric Power Construction No.3 Engineering

Company and the Beijing Starbecs Engineering Management Company. Tianwan NPP Phase II is the first NPP project to be constructed which is generally contracted by CNPE after Japan’s Fukushima nuclear accident. The opening ceremony of the conventional Island of Tianwan NPP Unit 3 is another major milestone of this project, marking that Tianwan NPP Phase II has been fully operated and entering the overall construction stage.


Environmental Impact Assessment Published - RMB 37.4 Billion to be Invested in Lufeng NPP

Environmental impact assessment of Guangdong NPP Phase I (Site Selection Stage) is to be published after being accepted by the environmental protection agency website, reported on April 23. The publishing time is from April 22 to May 1st, 2013 (ten days).

It was learnt that Lufeng NPP has been listed as an optional candidate site to be constructed in the national mid-and-long term nuclear power development plan during the 12th Five-Year Plan. This coastal site is located in Tianwei Mountain, about 8 km south of Jieshi town in Lufeng, Guangdong province. The site chosen for Lufeng NPP belongs to Lufeng city, governed by Shanwei city, Guangdong province on the administrative divisions. Lufeng city is located about 26km southwest from the site, while Shanwei city lies about 45 km to its west.

The assessment report revealed that Lufeng NPP plans to construct six pressurized water reactor nuclear power units of one million kilowatts each and two AP1000 units in the first phase. The total investment is about RMB 37.4 billion, in which the capital amount accounts for 25% and the environmental protection investment is about RMB 790 million.

Unit one of Lufeng NPP plans to pour the FCD in December, 2013, with a single construction cycle of 54 months and ten months apart for the construction of two units. Two units of the first phase are intended for commercial operation in June, 2018 and in April, 2019 respectively.

Source: http://np.chinapower.com.cn

54 目录

© Dynatom is a trademark of Dynabond Powertech Service Co., Ltd.

EDITORIAL STAFF

/ 编辑团队

CONTENTS目录55

58

61

71

88

76

79

81

84

65

68

基准测试：回转炉拆除活动分析

科技文章

HAF 政策

会议展会

新闻

核电词汇

专访

重点新闻

企业新闻

国际合作

核电站新闻

EDITORS / 编辑

Arnaud Lefevre-Baril / 百力 Bessie Wang / 王文贝

NEWS / 新闻

Qi Jia / 戚佳

TECHNICAL ARTICLES / 科技文章


EVENTS / 展会会议

Qi Jia / 戚佳

DESIGNER / 设计师

FangHua Design Inc. / 芳华设计公司

DYNABOND POWERTECH SERVICE

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版权所有。未经本刊物编辑和 / 或刊物内各部分来源允许，不得以任何形式、任何方法对本刊物内容进行复制。

必维国际检验集团核电部门经理张文印先生专访

法国电力集团深圳工程、采购、生产和研究中心

Bruno Marquis 先生专访

工程和采购部总经理美国机械工程师学会北京代表处首席代表、

ASME 亚太有限公司 ,执行总监张强先生专访



55 专访

DPS: 您能介绍一下您的个人背景吗？

张文印 : 我毕业于上海交通大学，获得了核能工程的学士学位。上海

交大是中国顶尖大学之一。我曾发表过几篇关于核反应堆燃料重载和辐射

防护的论文。

DPS: 您是何时加入必维国际检验集团的？如何加入的？

张文印: 2007年毕业后，我获得了加入必维国际检验集团(以下简称“必

维”)的宝贵机会。当时，必维对核电行业定位是一个具有战略拓展意义的

市场。之前中国核电有 15年的时间处于停滞不前的状态，而我们从中看到

了核电市场快速发展的巨大潜力。中国于 2005 年开始新一轮的核电建设计

划，并就三门核电站与海阳核电站与美国西屋公司签订了合约，必维也得

以把在中国核电项目中多年积累的丰富经验，以及欧洲、美洲的先进核电

技术和专业知识综合起来，进一步发展和巩固我们在核电市场的业务。

DPS: 大多从上海交大毕业的学生会选择工程设计公司。您的专长是堆芯设计，但是您为什么没有选择像中国核动力研究设计院这样的国有企业工作呢？

张文印 : 如您所说，设计院、中广核、国家核电等大型企业都是很好的

企业和发展平台。与他们相比，必维对职业发展的优势主要在于可以提供

很好的职业规划，这里可以让我迅速的接触更多的工业实践以及国际技术，

同时也有机会了解到核能以外的行业，如火电、水电、石油天然气等。

必维中国成立于 1994 年。新加入公司时，必维还没有独立的核电部门，核

电与热能、风能、太阳能等统一归属于电力公共事业部。

当时我是唯一一个负责核电市场的员工，不过这种情况很快得以转变—我

们开始扩大核电团队、拓展核电市场。我们为员工提供培训，并从法国总

部和美国公司邀请专家帮助我们提升中国核电团队综合实力。

DPS: 培训是在法国总部、美国公司还是在中国进行的？

张文印 : 当时所有的培训都在中国进行。但是在核电部门成立后，我

得到了去美国和法国接受高级培训的机会例如前往美国接受国家锅炉压力

容器检验师协会的培训并获得了该协会授予的核电检验师证书 (https://

www.nationalboard.org)。我现在是一名合格的 RCC-M标准培训师，同时还

参加了欧洲技术指令及工厂检验等技术培训。必维为中国团队提供最优秀

的培训资源，这样不仅能够有效减少成本开销同时也极大的推进了我们的

本土化进程。

DPS: 必维如何成为 ASME 标准认证方面的专家？

张文印 : 成为专家的唯一途径是通过学习和实践积累丰富的经验。必

维是最早从事核电 ASME 标准认证的机构之一。我们在中国有上百家获得了

ASME认证的压力容器制造商。且我们已经接到了多个ASME核电认证的订单。

必维目前在中国的为 AP1000 依托项目提供服务，该项目中的核电设备多采

用 ASME 标准。我们还为必维检验师提供美国核电标准的相关培训。

DPS: 成为一个合格的检验师和培训师需要多长时间？

张文印 : 对于相对简单的工作，我们可以很快就将具有一定工作经验

的人员培训成为合格的检验师。对于核电而言则需要相当长的时间。到现

在为止，我已经在必维工作了 5年，其中接受的培训时间累计有 3年，这

让我在不同的领域都获得了资格。在我工作的地点会有和的检验师的陪同，

这样就可以不耽误工作的情况下 (如在报告上签字 )接受培训。当然，专

家会对我的工作做出全程指导。这就是必维的工作模式：保证服务的同时，

对我们的检验师进行培训—工作和培训两不误。

DPS: 您认为哪方面的培训最吸引您？

张文印 : 关于学习方法的培训，也就是授人以渔。我刚参加工作的时候，

由于缺乏检查实践经验，我的指导老师给我制定了一套特别的教学方法：

他在交给我一些基础知识的同时，更教给我如何理解和自行探索这个领域

的知识，这让我受益匪浅。在必维，员工可以选择成为某一领域的专家，

也可以选择成为一个各方面都有所了解的通才，从而选择成为项目经理、

协调员或加入市场和销售部。就拿我而言，我不仅有核电方面的专业知识，

对其它领域也有一定了解。

DPS: 必维在中国核电市场的主要业务有哪些？

张文印 : 我们与美国西屋公司、阿海珐、阿尔斯通合作，共同负责质量

必维国际检验集团核电部门经理张文印先生专访

邮箱 : [email protected]

手机 : +86 180 1750 208

控制与质量保证。就 AP1000 项目而言，我们代表西屋电气公司为三门和海

56专访

阳四台反应堆提供服务，包括技术和质量支持、对所有供应商进行质保审计、

出厂验证和程序管理等。我们还为阳江、福清、方家山项目负责应急柴油

发电机的支持工作，从原材料到现场安装我们都会全程参与。我们还负责

岭澳 1期和 2期项目的反应堆冷却泵、反应堆压力容器、反应堆内部构件

及蒸汽发生器。我们代表阿海珐负责质量检验和质保审计。2007 年我们负

责秦山反应堆顶盖更换的检验工作，这属于我们 OPEX 服务的一部分。当核

电站处于大修期或设备需要更换时，我们会提供专业的检验监督服务。

就秦山项目而言，我们的客户在时间和质量把控方面要求非常严格。业主

要求更换的部件要完全符合他们质量标准，且必须在规定期限内交付。然

而要将先进的国际标准与老旧的技术结合起来是一个非常大的挑战。必维

在对应这类项目上有着丰富的经验。

DPS: 你们与中广核是否也有合作？

张文印 : 我们与中广核的建立了良好的合作关系，广核高度认可对必

维的全球核电经验，我们也在积极探索如何进一步开展合作。

DPS: 贵公司与中核集团有合作吗？

张文印 : 中核集团有许多项目，如秦山、福清和方家山项目。我们主

要与中核集团在中国的项目合作。

DPS: 您能否简单介绍一下在核设备及其它材料运输方面，必维是如何实施检验的？

张文印 : 我们集团把该类检验归类为“全程监控”。在部件几近完工时，

需要考虑运输部件采用的包装类型，如海运、陆路、铁路运输等包装规格

均不相同。因此必维将会按照运输方式检查包装规格及分类标记，以确保

不会出现错包、错放等情况的发生。同时，在产品交付现场，我们将对交

付的产品进行检验，以确保部件的完好无损。

DPS: 必维的业务方向是否包括进口设备或国内产品？

张文印 : 是的，这两个方向我们都有涉及。在中国我们更多的业务是

与进口部件相关，原因是进口设备的包装要求更为复杂，风险更高，业主

和承包商也对进口设备的要求更为严格。我们在中国国内产品上也积累了

丰富的经验，如之前提到的 AP1000 项目，必维与该项目的多个制造商联系

密切，能够帮助他们按照客户要求对产品进行改进。

DPS: 这些要求是由承包商还是中国国家核安全局提出的？

张文印 : 国家核安全局会将要求通知给承包商，进而通过承包商、设

备制造商等的质保体系传递到我们。必维的一项重要的工作就是确保所有

跟项目相关的公司、企业、机构严格按照承包商的要求执行，同时该要求

是以文字形式送达各个单位。必维需要确保所有的文件及方案都有效执行，

并且获得客户的认可。

DPS: 贵公司是否会向承包商提供技术规范方面的建议？

张文印 : 我们有能力提供咨询服务和技术建议。在法国，我们是法国

核安全局（ASN）的授权代表，同时也十分熟知 RCC-M 规范，我们可以根据

我们的经验及获得的反馈建议 AFCEN 修改规范。

DPS: 必维最近加入了核能行业协会，你们加入该协会的主要原因是什么？

张文印: 核能行业协会是中国最大的核电企业联盟，在行业内享有盛誉。

必维在核电行业的检验、检测和认证方面拥有丰富的经验，我们的专业人

员也在行业中工作多年。我们希望能够为中国核能行业的复兴尽一份力，

与中国核电企业共同成长。同时我们希望借助核能行业这个平台，与智者

并肩同行，分享行业的信息和经验。

DPS: 贵公司于 2007 年在中国开展新业务，这期间有没有遇到阻碍？

张文印 : 首先我们是幸运的，我们有幸见证了中国核电的再次复兴并

参与其中。我们有来自欧洲、北美洲的专业核电知识，有专业的服务产品

和优秀的人才。在业务开展方面，当然最初我们遇到了品牌推广的挑战，

我们需要花更多的时间让国内的核电行业了解和接纳我们。因为当时在国

内还没有专门从事检验、检测和认证的机构。另外，国内有些活动只能由

特定的单位完成，环境影响评估、调试、运营服务、退役等。因此必维即

便在国际上有丰富的经验和业绩，也无法短期内进入这些领域。

DPS: 福岛事故对必维产生了什么样的影响？有没有客户针对环境影响评估对你们的服务提出特殊的要求？

张文印 : 我们都能够看到福岛事故对核电行业产生了巨大的影响。我

个人认为，这次事件的正面意义在于为核电行业敲响了警钟。人们意识到

需要加强对核电行业的管控。确保核电的安全与质量要远比快速发展核电

重要。这是核电发展的基本保证，也是核电行业对人民的承诺。因此福岛

事故对于必维来说既是一个机遇也是一个挑战，我们必须准备好提供更为

必维国际检验集团第三期 RCC-M 2007 培训

57 专访

优质的服务满足市场需求。我们需要预见到中国本土公司及项目的需求。

DPS: 目前中国尚未在国内形成一条与设备安全相关的供应链，必维是否有这方面的服务？

张文印 : 必维十分擅长于帮助供应商完善其管理体制，确保符合行业

的期望。业主和承包商也越来越多的要求我们对他们的国内供应商进行培

训，帮助他们熟悉相关的规范和准则。中国供应商的车间配备了一流的设

备和优秀的员工。我认为中国制造商需要了解如何更好的管理工厂，以确

保他们的产品符合业主对质量的要求，并确保产品在业主规定的时间内完

成交付。

DPS: 中国的承包商主要采用的是法国的RCCM/RCCE 标准和美国的 ASME/ IEEE标准。必维有没有针对此类标准的培训？

张文印 : 我们有关于 ASME 标准和 RCC 标准的培训。更重要的是我们也

具有实践的经验。我认为只通过一节标准方面的培训辅导很难起到一个长

期的效果，因为课堂培训主要是知识理论方面的。培训的主要目的是帮助

客户理解产品需要遵循的标准，并对其产品规格的改进方面给予支持。我

们会对与必维有项目合作的客户在标准和规范方面提供支持。

在 ASME 核电认证方面，我们帮助银环钢管获得了 ASME 标准的证书。同时

我们也提供 RCC标准的培训和咨询服务。

DPS: OneCIS 是必维旗下一家获得授权的保险代理公司，负责为客户按照 ASME 标准提供检验服务。而中国下一步将会大力发展AP1000 第三代核电技术，那么与 ASME 相关的客户是不是有所增加？

张文印 : 必维获得授权为中国 ASME 相关项目提供服务。OneCIS 是我们

集团的下属公司，并帮助必维管理授权检验业务和授权检验师。我们对于

ASME 相关业务的发展十分乐观，中国具有巨大的供应商群体，因此在认证

方面潜力不可小视。

DPS: 贵公司在中国 AP1000 项目中担任什么角色？

张文印 : 我们代表西屋公司提供现场质量监督和质保服务。我们在核

电站建造项目提供现场技术支持，并对中国的供应商实施质量监督和定期

质保监查。

DPS: RCC-M 标准和 ASME 标准，哪个将成中国市场的主导方向？

张文印 : 这个问题我很难回答。因为供应商可以通过培训快速了解 RCC

标准，且大多中国供应商都有与中广核合作的经历，他们按照 RCC 标准建

立了一套程序。中广核工程有限公司定期给其主要的供应商进行 RCC 标准

培训。因此，RCC系统的供应链更加成熟。这也就是为什么有很多客户要求

进行 ASME 方面的培训。作为供应商，他们需要同时了解掌握这两个标准。

DPS: 必维是否与中法核工程与技术学院有联系？

张文印 : 2011 年我们资助了该学院的一个 5年教育计划项目。必维希

望参与培养中国核电人才，为中法项目做好准备，同时必维也有面向中国

学生的法国项目。我们认为在中法两国建立联系非常重要，很荣幸能成为

这个项目的一分子。

DPS: 您认为必维将来会参与核电哪些领域的项目？

张文印 : 我认为将来会有许多与土建服务和核电站大修服务相关的项

目机会。我们也希望能够帮助中国核电尽快走出国门，无论是核电设备，

还是完整的核电站项目出口。

DPS: 对于新进入中国市场的企业，您有什么建议？

张文印 : 对于新进入中国市场的企业，首先要做的是了解本国文化，

建立本土化的团队，采用战略方针扩大中国市场。我认为最关键的是要了

解本土的市场结构和本国文化。

点击下载工业与设施事业部电子新闻报 /《BV EXPRESS》电子杂志

http://www.bureauveritas.cn/wps/wcm/connect/bv_cn/Local/Footer/Home/

58专访

以过时的设备为例，我们现在处于进退两难的局面。由于设备陈旧，其原

有的供应商已经退出该市场或者是该设备应经停产。我们有两个方案可以

解决这一困境：或者在法国建立该部件的全套供应链，或是选择从海外市

场（如中国）寻找类似部件。我们选择中国的原因是，中国现在核电的发

展进程类似于法国七八十年代的核电项目。由于中国核反应堆国产率的要

求，中国的制造商采用的是法国标准和规范，如 CPR1000 就是在法国技术

的基础上创新的。当一个部件在法国已经过时很难找到时，EDF 可以在中

国找到同样的部件，按照 25 年前的法国规范制造的。

DPS：谁负责对供应商进行认证？

Bruno Marquis：EDF 拥有专业的操作技术部门负责资格认

证。该部门对供应商进行评估确保其有满足我们商业、技术和环境要求的

能力。部门将根据 EDF 的需求对供应商进行审查和资格认证。

DPS：EDF、Framatomeand 和 Novatome 是 AFCEN（法国核岛设备设计、建

造及在役检查规则协会）的始创者，请问 AFCEN 是否适用于外国机构，例

如中国核电技术研究院（CNPRI）？

Bruno Marquis：目前，中广核已经是 AFCEN 的成员之一，任何公司都可

成为其成员，例如，日本三菱公司、西屋电器和主要的核电公司都已加入

AFCEN。RCC 标准规范时刻在变动，最新的版本发布于 2012 年，该版本采

纳了制造商、设计师和运营商的信息反馈。加入了 AFCEN 的中广核不仅本

身使用规范与标准，同时也为标准的更新作贡献。

DPS：大多数中国工程公司在新的核电项目中（如 ACPR1000、ACP100、ACP650、ACP1000）多采用 RCC 标准。那么未来中国能否拥有属于自己的 RCC 标准吗？

Bruno Marquis：中国同法国、日本、南韩、美国、德国和

俄罗斯等国家，都会拥有其属于自己的标准。八十年代的法国使用 ASME

DPS：您是何时加入法国电力集团的？

Bruno Marquis：我在 1995 年 4 月进入法国电力集

团，并加入了里昂的核工程部（在法国称为 DIN 部门，是“Division

Ingenierie Nucleaire”的缩写），在来北京之前，我的大部分职业生涯

都是在那里度过的。

法国电力集团在中国市场的壮大对我的职业生涯有很重要的影响：因岭澳

二期核电项目，我被派往至中国。中广核集团负责此项目管理并向中核集

团下的中国核电工程有限公司提供工程保障，我也是其代表之一。我们负

责项目管理和技术审查，尤其是在安全、运营规则等方面提供技术支持。

DPS：您被派遣到中国核电工程有限公司工作有多长时间了？

Bruno Marquis：我在北京待了三年半，后来因为台山项目

我又回到了法国。当时EDF与阿海珐成立了一家名为SOFINEL的合资公司，

负责台山项目的设计工作，我在该公司担任系统与设备部的负责人。

DPS：您作为 PIAP 工程采购不的负责人，能否为我们介绍一下 PIAP 的使命和您在 PIAP 的职责？

Bruno Marquis：法国电力集团建立 PIAP 技术中心的目的

是为其在 EDF（中国）公司提供 EDF 全部的技术范围保障，包括采购、工

程、研发及运营与维护。PIAP中心能够为EDF在中国的核电项目提供保障，

例如，项目管理，专业知识，销售代理，技术咨询等。我主要负责的是工

程与采购事宜。

DPS：您们的采购活动进展如何？

Bruno Marquis：我们是采购行业的佼佼者，我们的职责是

配合巴黎总部对中国市场进行评估。我们正在研究中国市场，希望从中找

到解决方案。

法国电力集团深圳工程、采购、生产和研究中

心工程和采购部总经理

Bruno Marquis 先生专访

Email：[email protected] Mobile: +86 18200980713

59 专访

准则作为 RCC-M 的制定的基础。很明显中国也将会用现存的规范来设计其

自己的标准。RCC 准则因其“独立性”而为大多数制造商所采用。与 ASME

标准不同的是，RCC 标准内容非常详细，不需要第三方制造商提供参考信

息。

由于缺乏丰富的设计经验，中国核电公司通常被认作是新起之秀。因此

RCC-M 的部分标准对这些公司的制造环节起到了强制性的规范作用。而对

于一个新的设计公司来讲，执行 ASME 的标准并非易事。因此像国家核电

技术公司这样年轻的集团不仅要求制造商遵循 ASME 标准，同时 RCC-M 的

部分标准被列入清单，对此要求我并不感到惊讶。

DPS: RCC 准则在中国是否有长期的或是周期性的培训？

Bruno Marquis：当一个企业收到来自 EDF，Areva 或是其

他公司的采购订单时，就必须按照最新版本的标准制定订单，通常来讲

这是强制性的。生产商可以在 AFCEN，或是必维国际检验集团（Bureau

Veritas）等公司进行培训，也可以自己来完成。

DPS：SNPI（苏州核能研究院）在 RCC 标准培训中的作用是什么？

Bruno Marquis：SNPI 为中国公司提供一些关于 RCC-M 标

准的培训。SNPI 与 AFCEN 正在商讨组建 RCC 准则使用用户的相关事宜。

DPS: 贵公司是否与诸如 Bureau Veritas、Apave 和核学院等这样的公司、机构有联系。哪些公司或机构获得了 AFCEN 在中国核电市场的认证授权？

Bruno Marquis：PIAP 不提供培训业务，但是我们经常参

加法中电力协会定期组织的各种活动，研讨会和会议等。

DPS：去年三月，AFCEN 组织了三年一度的规范与标准大会，很多中国企业出席了会议，那么该大会的目的是什么？

Bruno Marquis：确实有很多中国生产商和官员代表团出

席了此次会议，人数达 20 人之多。在该会议举办前，很少中国公司知道

AFCEN，这是自会议举办以来第一次有如此多的中国代表参会。这就表明

了 RCC 标准在中国市场的重要性以及如今 AFCEN 在中国的认可度。

DPS：贵公司有没有参与台山项目？

Bruno Marquis：PIAP 将会与法国的事务部门共同合作，作

为参与中广核 /EDF 台山合营公司的支撑单位。我们在法国培训过的中国

工程师也可以为台山项目提供专业的技术知识，例如一些关于中国技术规

范和方法的分析。

DPS：我们知道台山核电合营公司使用的是RSE-M 2010 标准，您能告诉我们关于它的更多的信息吗？

Bruno Marquis：AFCEN 采用该项标准来监管与安全性能相

关的设备，所有设备都必须遵循 RCC-M 标准。该准则应用于运行中的核电

站，也就是说所有设备定期的维护与控制等都会被记录下来。现在 EDF 在

法国的所有核电站都在用这个标准。

DPS：2010 年，法国和中国在中国珠海联合创建了中法核工程与技术研究院（IFCEN），该研究院是否有针对 RCC 标准的相关课程？

Bruno Marquis：IFCEN 两年前刚刚成立，按照项目规划来

看，预计于 2014 年或 2015 年开设 RCC 标准的相关课程。两年前开始，我

们与这个研究院的管理者有着密切的联系，并且为该院的学生提供核电相

关的工作岗位。

DPS：关于采购方面，您是怎样看待快速扩张的中国市场的？

Bruno Marquis：对于 EDF 乃至法国来讲，快速增长的中国

市场既是机遇也是挑战。它使我们受益于技术发展，同时也使我们面临着

保持这个不断增长的市场始终符合我们要求的挑战。

最后，我想说的是EDF必须解决关于采购的具体问题，而中国能提供一些解

决方案，但是我们的意图并不是在中国所有的细分市场建立完整的供应链。

核电市场是一个长期市场，任何生产商都需要时间去研发产品并且验证产

品质量。从安全性和可用性角度讲，EDF 运营商最为关注的是技术专业知

识和长期的售后服务（一般为运行 40 年，甚至 60 年）。

中国有自己的供应链；法国供应商不仅有独特的专业知识，而且法国企业

不断提升产品质量，具有强大的创新力，及满足复杂认证标准的能力。因

此法国众多中小企业（如法中电力协会的成员）研发的高科技产品也在中

国乃至世界范围内都有供应。

60专访

诺本集团是国际领先的投资贸易促进机构，致力于发展欧美发达经济体和新兴发展经济体之间的国际投资和贸易，及各领域先进技术的交流。自

1998年进入中国市场以来，在政府部门、科研院校、行业协会及世界500强企业的支持下，诺本每年成功在华举办40余次国际投资和贸易发展峰会，

已成为持续发展的中国市场和国际先进技术及优质资本之间合作沟通的有效桥梁，并逐步成为最具规模和影响力的投资贸易促进机构之一。

峰会背景：

核能已成为人类使用的重要能源，核电是电力工业的重要组成部分。由于核电不造成对大气的污染排放，在人们越来越重视地球温室效应、气候

变化的形势下，积极推进核电建设，是我国能源建设的一项重要政策，对于满足经济和社会发展不断增长的能源需求，保障能源供应与安全，保

护环境，实现电力工业结构优化和可持续发展，提升我国综合经济实力、工业技术水平和国际地位，都具有重要的意义。

2012年10月24日，国务院常务会议讨论并通过了《核电安全规划》和《核电中长期发展规划》，根据WNA预测，到2020年中国核电装机将达

67.3千兆瓦。随着核安全“十二五”规划的正式公布，中国核电的重启之路又迈进了一步。为探讨“后福岛时代”的中国核电政策，如何安全高

效发展核电，关注核电新项目审批的重启概况及中国未来核电发展规划，交流先进的国内外核电装备制造技术，“第八届中国核电安全发展论

坛”将于2013年7月4日至5日在山东烟台市举行。

第八届中国核电技术与投资论坛2013年7月4日至5日,山东烟台

•一对一商务会谈：向真正的决策者、负责人推介和销售您的服务和产品。他们正在为现在和即将开建的项目寻找行业解决方案。

•有限的演讲机会：通过度身定制的演讲，向客户展示企业的专业特长。

•展位：通过展位展示企业的产品特性，同时与会议代表进行直接交流。

了解详情请联系

陈玉 Sharon CHEN

第八届中国核电安全发展论坛组委会

电话：+8621-60851000-313 传真：+8621-6192-1905 电邮：[email protected]

会议官网：http://www.noppen.com.cn/upcoming/L1313/CN/index.asp

会议特色：

主办方：

主要议题：

•《2020年核电中长期发展规划》与《核电安全规划》解析

•中国电站未来规模目标、审批区域、技术路线

•中国核电新项目发展的前景展望

•掌握三代核电关键核心技术

•核电设备制造产业发展现状与趋势

•世界首座四代核电站：华能石岛湾高温冷气堆项目进展情况介绍

•中核核电集团核电站建设的最佳实践介绍

•中广核集团未来发展战略

•自主研发ACP1000三代核电技术总体布置方案

•国内核电站项目进展情况与未来规划

• ……

61 专访

建立更加合适的第三方检验体系和更加完善的核安全体系。我们也希望通

过努力能够帮助美国的科技界工业界和相关部门能够更加密切的开展相关

工作。

DPS: 如何参与 ASME 核电规范和标准的制定与修改？

张强：ASME 标准是一个开放体系，所有人都能参加，无需缴费注册，

唯一区别是非会员在未得到相关委员会正式接纳前没有表决权。考虑到地

理位置和操作习惯，ASME 为北美以外的专家制定了一个特别身份，叫做

援助代表计划，相当于一个团体会员制。每年一个固定的人去参加 ASME

会议不太现实，但是作为一个团体，每年可以有不同代表去参加，这样可

以增加各团体连续参加ASME例会的可能性。ASME的服务对象可以用“能源”

二字概括，具体来讲，第一石油石化，因为其大量承压设备需要 ASME 标

准支持，第二是电站设备，包括核电设备。

ASME 标准需要与时俱进，符合经济发展与实际情况，因此 ASME 每两年修

订一次，修订幅度较大。ASME 有 500 多个标准化委员会，在全世界有四、

五千志愿者和专家来参与 ASME 的修改与制定。成为 ASME 正式会员，可

以通过两种方式参与 ASME 的活动，一个是亲自参加会议，或者通过 Code

& Standard Connect（C&S Connect）这一软件系统全天候参与，C&S

Connect 是一个数据平台和工作平台的结合，作用是将 ASME 标准的制定

和修订的进程全部显示在这个平台上，获得授权的人可以实时浏览标准的

制修订过程、互动发表意见并对通过这个平台标准的最终方案进行网络表

决。

中方专家同样可以通过 C&S Connect 参与 ASME 标准的制定，这是一个良

性的互动，ASME 非常感谢中方的机构和专家能够如此积极主动参与 ASME

标准的制修订工作，这一工作的进程说明 ASME 标准融入了中国专家贡献

的智慧和经验。随着这个技术的推进，中国机构的贡献会越来越多，话语

DPS: 您能否给我们简单介绍一下您的个人经历及在 ASME 的职位？

张强：我曾在原机械工业部工作，后转到机械工程学会，2006 年加入

ASME，担任北京代表处办公室首席代表，最近又接任 ASME 亚太有限公司

的执行董事，帮助推广 ASME 的服务与活动，促进 ASME 同中国相关对口单

位合作伙伴之间的合作，包括但不仅限于核电。

DPS: ASME 中国代表处的业务范围有哪些？

张强：ASME 中国代表处正式成立于 2008 年，但是早在 2005 年初就联

合美国石油学会，美国材料与测试学会和加拿大标准协会美国分会成立了

一个标准与合格评定联盟。2006 年底，我加入 ASME 时，担任联盟的运营

总监，负责 4 个学会的工作。2008 年联盟的工作结束，这几家独立成立

代表处之后，我就全职为 ASME 工作。ASME 在北京的代表处目前有 4 人，

ASME 服务的对象是能源行业、装备制造业、工程技术界和教育界。

简单说，ASME 北京代表处只是起到一个桥梁作用，第一是把 ASME 介绍给

中国，第二是把中国介绍给 ASME。另外，我们希望通过努力获取真实的、

正面的信息来帮助相关合作方、合作伙伴做出正确的选择，从而达到一种

双赢的局面。我们在中国的工作范围包括学术活动、咨询服务、培训、出

版发行，合作举办会议研讨会，参加中国行业团体或协会举行的展览会。

ASME 中国代表处与政府部门、行业团体、高校及相关企业建立了良好的

关系，例如发改委、能源局、工信部、科技部、教育部、国家核安全局、

中国机械工程学会、中国机械工业联合会、中国核学会、清华大学、上海

电气、哈尔滨电气等。我们与核电企业中核集团、中广核、国核技等都有

很好的关系。

截止到 2012 年 7 月，中国大陆地区 ASME 持证厂商有 660 家，其中持有核

证的厂商有 29 家。介于核电在中国的重要地位，今后，我们的工作重点

之一就是支持中国的核电建设，支持中国核电标准的建立健全，支持中国

美国机械工程师学会北京代表处首席代表

ASME 亚太有限公司执行总监

张强先生专访

邮箱：[email protected] 电话：010-51096032

62专访

权会越来越强，相信也将有助于建立健全中国自己的核标准规范以及建立

中国自己的第三方认证机制。有些机构一下子介入到这么深有困难，我们

还有别的选择，一个是贡献会员，会员有意见就提，没意见就不提，另外

还有观察员，他们不承担任何义务责任，当然他们获得的授权权限也不尽

相同。我建议中国的单位和机构要有更大的魄力和勇气来鼓励支持自己的

专家参与 ASME 的活动，第一时间掌握最新的动态，这对我国的核电发展

有很大益处。

DPS: ASME 中国国际工作组是一个什么样的组织？职责范围是什么？

张强：ASME 的标准在世界 110 多个国家使用，ASME 的合格评定服务得

到 90 多个国家认可，许多国家直接把 ASME 的标准和认证作为自己官方强

制性的标准和认证。ASME 的标准与认证工作不仅仅为美国服务，同时为

世界上许多国家和地区提供服务。ASME在近期给自己规定了三大的使命：

第一是服务能源工作；第二是发挥国际化的作用；第三是人才培养，尤其

是劳动力培训。希望通过国际交流与合作，创造更多的便利条件来帮助非

北美地区的专家和单位机构参与 ASME 的工作，能够真正成为 ASME 标准开

发制定体系的组成部分，因为我们希望有更多的渠道和方式来了解、讨论、

分析和反馈各地方在使用 ASME 标准中所遇到的问题，也希望通过建立一

个新的工作机制来帮助各个地方在因地制宜使用 ASME 标准过程中具有更

多的针对性，因此，我们提出了成立国际工作组（International Work

Group, IWG）这个概念。

工作组对应不同的上级委员会，目前已经成立的中国国际工作组对应于锅

炉压力容器标准第Ⅲ卷委员会，也就是核卷。这个工作组不仅仅是美国方

面提出来的，更多的是中方在建设新的核电项目过程当中、在引进消化吸

收三代核电、特别在开发自己的三代核电当中，越来越觉得需要对 ASME

的标准规范有更多的了解，所以中方也希望以比较积极的姿态和主动地方

式进入到 ASME 标准的制定和修订当中去。于是就成立了这个工作组，作

为 ASME Ⅲ卷委员会在中国的延伸，它拥有在制定修订 ASME 核标准过程

的话语权、建议权、解释权。目前，这个工作组正在逐步丰富自己的经验，

完善自己的工作规程，积极介入 ASME 的相关标准制修订和解释工作，进

而支持中国核电建设。这个国际工作组现在有 39 位成员，分别来自政府

监管机构、设计、工程建设和设备制造单位，中核、中电投、华能、哈尔

滨电气、上海电气、东方电气、一重、二重、上海成套院、上海核工院等

均是工作组成员。秘书处挂在上海核工院。

这个工作组成立已经两年，每一个季度开一次会，效果非常好，大家讨论

热烈，认真投入。ASME 的委员会和下属组织构成遵循这样的比例：1/3 来

自设计和研发部门，1/3来自于设备制造部门，另外 1/3来自于用户单位，

还有很小部分来自于政府部门的监管机构。之所以特意维持这个比例就是

要确保 ASME 的标准与规范建立在公平公证和透明的基础上，所以我们的

构成一直如此。中国的工作组也基本维持这个比例。

各种标准都有各自存在的价值。中国也在开发完善自己的核电标准，通过

拥有中国自己的自主知识产权和核电站技术，中国一定能够建立完善的核

电标准体系。我们衷心希望 ASME 标准和中国的核电标准能够相互融和，

ASME 的标准愿意为中国核电建设服务，愿意为中国建立自己的标准体系

贡献力量。

中国的核电标准建设任重道远，需要各界倾力支持。ASME 真诚支持中国

完善自己的标准规范体系。谈到任重道远，我个人以为必须从基本原则抓

起：第一，标准应由生产实践得来，而不是闭门造车；第二，标准要建立

在真正的民主的基础上，避免被各种利益左右；第三，中国的标准要符合

中国的核电发展的需求和核电建设的具体实践；第四，政府在标准建设过

程中应当发挥主导作用。中国的核电建设是由政府主导的，相应的标准工

作同样需要政府引导掌控。国家能源局领导下的国家能源核电标准化委员

会的工作稳步推进，标准框架日趋完整。作为以行政化的方式制定标准的

模式，中国的成绩是显而易见的。如果政府完全撤出来，有可能会使真个

事情停滞不前，因为我们没有良好的社会中介组织基础，也没有真正的第

三方独立机构，所以政府的把关和资助是很重要的。

DPS: ASME 是否有计划针对中国的核电市场制定一个核标准？

张强：ASME 不会单独为中国市场制定一个核标准规范，但将同中国机

构和专家合作，进一步完善 ASME 的规范，进而更好地为中国核电建设事

业服务。已经有两个ASME标准委员会在中国成立了中国国际工作组（IWG），

目前正和全国锅炉压力化标准委员会合作，筹备组建第八卷（压力容器）

标准委员会的中国国际工作组。与此同时，还在与多家核电机构协商，尽

早组建第十一卷（在役检查）标委会的中国国际工作组，以便使 ASME 标

准增加更多的中国元素。至于在中国自己的核电标准建设方面的具体合作，

ASME 尊重中方的意见并将一如既往予以配合。我个人希望大家能够以一

种超脱的态度判断什么样的标准对人类的核电建设具有更大的价值。

作为一个国际性组织，ASME 希望通过自己的标准平台，加强与中国专家

和更多非北美地区的专家的交流沟通，以获得更多共识，这也是 ASME 邀

请更多的机构和个人加入ASME各个委员会和组建中国国际工作组的原因。

希望今后在中国建立更多的 IWG。

63 专访

DPS: 您对 ASME 未来在中国核电行业的发展有什么建议？

张强：我没有资格提出什么建议的，作为一个老百姓，希望万事以实

事求是，以服务人民为最高原则。在安全问题上一定实事求是，切忌自欺

欺人，核电行业是没有后悔药可吃的行业。在核电站建设方面，为老百姓

着想，尽可能避免犯无法弥补的错误。要以老百姓的利益和安全为最高原

则.如果说对核电发展有什么期望，我认为不要操之过急，一步一个脚印，

带着一个端正的态度，多注意观察学习其他国家是怎么做，并且一定搞明

白为什么这么做。尽可能派大量青年人才到核电发达国家去学习和培训，

真正深入到其他国家的核心技术体系中去了解他们的真谛。中国核电发展

从长远来说，需要进行合理规划，不用紧锣密鼓，因为核电建设绝不是一

蹴而就的事情。

DPS: ASME 和 RCC-M 的区别在哪里？ASME 是否只适用于 AP1000 堆型？

张强：ASME 是几乎所有核电标准的源头。RCC-M 也源于 ASME 的锅炉压

力容器规范。ASME 的规范更加强调为用户提供方法和平台，以便用户可

以基于自己的需要开展自主创新。ASME的核标准支持所有核技术的发展，

不仅仅是 AP1000。

DPS: ASME 的角色和作用与刚进入中国市场相比是否发生了变化？

张强：ASME 的角色和作用与 70年代 80年代相比没有什么太大的变化，

我们一开始就得到友好的接受，大家都很珍惜 ASME 的价值，花费很多精

力来取得 ASME 认证，很多研发机构都鼓励他们的员工参与 ASME 的各种会

议、递交论文。国家质检总局特种设备监察局安排他们的下属机构审核员

到ASME实习，从80年代到现在都有很多人考ASME的授权检验师。两年前，

中国特种设备检测研究院派出 120 多个审核员报考 ASME 的授权检验师资

质，并组建了第一个中国本土授权检验机构。如果说变化，可以说我们变

得更加透明了，同中方合作伙伴更加推心置腹了，可以更加坦诚地交流了，

这样对双方做出的决定决策有了更好的保障。在核电领域，跟过去对比，

我们跟中核集团、中国核学会、中国核能行业协会、国家核电和中广核等

单位的关系一直很好。随着中国核电建设的发展，大家对 ASME 规范的需

求也越来越大。

DPS: ASME 在中国核电领域有哪些培训和认证机构？

张强：清华大学核研院获得了 ASME 授权，在中国开展核电标准与规范

的培训。ASME的培训班的特色之一是要求小班培训，每个班不超过25个人，

以保证老师同每个学员都有直接沟通的机会。清华大学核研院的培训是非

常正规、有价值，能够真正帮助解决问题，培训证书也是由ASME颁发的。

国内其他单位也有兴趣成为ASME的授权培训机构，但是，考虑到培训质量、

投入成本和耗时等因素，ASME 对授权培训机构比较慎重。核电行业的培

训工作的意义重大，尤其是相当多的单位和项目使用 ASME 标准和相关技

术文件，如果碰到关键问题还是要从 ASME 标准中去找答案。ASME 的标准

内容和结构都是很独特的，需要专业人士来诠释 ASME 标准，培训是一个

有效地手段。零星的拼凑理解一套标准是有害的，必须通过严谨严格的培

训来确保对标准的准确理解。

DPS: 目前中国核电行业各种标准并存，除ASME 还有法国的 RCC-M，俄罗斯的标准和加拿大的标准，您个人怎样看待这一现象？这对中国的核电发展有何影响？

张强：众多标准在中国并存，孰优孰劣很难做出评论。但是我个人认

为多种标准在一个国家并存不一定是好事，尤其作为公共投资项目，过多

标准体系并存对物力、人力资源、财力消耗很大。标准化的目的是统一、

准确、化繁为简，希望各种标准互相借鉴和采纳，避免资源的浪费。ASME

标准只是众多标准之一，它的权威性同样是通过时间和实践得到验证的。

64专访

65 HAF 证书

第一章　总　则

第一条　为了加强民用核安全设备焊工、焊接操作工的资格管理，

保证民用核安全设备的焊接质量，根据《民用核安全设备监督管理条例》，

制定本规定。

第二条　本规定适用于民用核安全设备焊工、焊接操作工的资格管

理。

第三条　从事民用核安全设备焊接活动的焊工、焊接操作工依据本

规定参加考核并取得资格证书后，方可从事民用核安全设备焊接活动。

第二章　机构与职责

第四条　国务院核安全监管部门负责核准颁发民用核安全设备焊工、

焊接操作工资格证书，其主要职责是：

(一)选定民用核安全设备焊工、焊接操作工考核中心(以下简称“考

核中心”)；

(二)组织制定焊工、焊接操作工考试大纲、基本理论知识考试题库，

并组织焊工、焊接操作工基本理论知识考试；

( 三 ) 监督检查考核中心的考核和管理工作；

(四 )审查考核中心的考试计划和考试结果，并向考试合格的焊工、

焊接操作工颁发资格证书；

( 五 ) 归档和保存持证焊工、焊接操作工的有关资料。

国务院核安全监管部门可以根据需要设立民用核安全设备焊工、焊

接操作工资格鉴定委员会，具体履行相关职责。

第五条　国务院核安全监管部门对符合下列条件的单位，可以选定

为考核中心：

( 一 ) 建立了健全的焊工、焊接操作工考核质量保证体系，具有完

善的考核和管理制度、考试细则、满足考试要求的焊接工艺规程和专项

理论知识考试题库等；

(二)具有5年以上的核级焊工、焊接操作工考核业绩，且考核焊工、

焊接操作工不少于 300 人次；

( 三 ) 具有与拟从事的焊工、焊接操作工考核活动相适应的场地，

包括技能操作考试场地 ( 至少 20 个工位 )、理论考试教室、钢材库或者

试件库、焊材库、检验场地、档案库或者资料库等；

( 四 ) 具有与拟从事的焊工、焊接操作工考核活动相适应的设备，

包括焊接设备、焊条和焊剂烘干设备、试件和试样制作设备、理化检验

和无损检验设备、热处理设备及测量工具等；

( 五 ) 人员组成至少包括：工程师职称以上的专职焊接专业技术人

员 3名，专职核Ⅱ级以上表面和体积无损检验人员各 1名；

( 六 ) 具备组织焊工、焊接操作工考试和管理焊工、焊接操作工焊

接档案的能力。

第六条　考核中心负责组织实施焊工、焊接操作工专项理论知识和

操作技能考试，其主要职责是：

( 一 ) 制定考试计划；

( 二 ) 审查报考焊工、焊接操作工的资格；

( 三 ) 确定专项理论知识考试内容和操作技能考试项目；

( 四 ) 制备和检验考试试件，并评定考试成绩；

( 五 ) 发放焊工、焊接操作工钢印；

( 六 ) 编制或者确认焊工、焊接操作工考试用焊接工艺规程；

( 七 ) 建立并管理焊工、焊接操作工档案。

第七条　拟从事民用核安全设备焊接活动的焊工、焊接操作工，应

当向考核中心提出考试申请。申请考试的焊工、焊接操作工应当具备下

列条件：

( 一 ) 具有初中或者初中以上学历；

( 二 ) 身体健康；

( 三 ) 有能力按照焊接工艺规程进行操作；

( 四 ) 有能力独立担任焊接工作。

第三章　考试内容和方法

第八条　焊工、焊接操作工考试包括理论知识考试和操作技能考试。

第九条　焊工、焊接操作工理论知识考试包括基本理论知识考试和

专项理论知识考试。

拟从事基本理论知识未包括的特殊焊接方法和母材种类的焊接活动

的焊工、焊接操作工，在参加操作技能考试前，还应当通过专项理论知

识考试。

民用核安全设备焊工焊接操作工资格管理规定（HAF603）

66 HAF 证书

焊工、焊接操作工基本理论知识考试合格有效期限为 3年。

第十条　焊工、焊接操作工基本理论知识考试应当包括下列内容：

( 一 ) 核电系统基本知识 ( 包括辐射防护方面的知识 ) 和核电质量

保证基本知识；

( 二 ) 民用核安全设备知识，包括设备类别和核安全级别，有关制

造标准和焊接规程，焊接接头分类原则和要求，常用母材和焊材、焊接

方法的特点和主要制造技术要求 (包括热处理和无损检验基本知识 )；

( 三 ) 焊接设备、装置和测量仪表的使用和维护要求；

(四 )焊接接头的形式、性能及其影响因素，焊缝代号和图样识别；

( 五 ) 焊接缺陷的产生原因以及防止措施；

( 六 ) 焊接应力和变形的产生原因以及防止措施；

( 七 ) 焊接安全技术。

第十一条　焊工、焊接操作工专项理论知识的考试内容应当根据特

殊焊接方法和材料特点确定。

第十二条　考核中心应当根据焊接方法、试件形式、母材类别、焊

接材料、焊缝形式、焊接位置、试件规格尺寸、焊接要素(衬垫、单面焊、

双面焊 )等，确定焊工、焊接操作工操作技能考试项目。

第十三条　焊工、焊接操作工操作技能考试试件的数量应当符合要

求，不允许多焊试件从中挑选。

试件的制备和焊接应当满足下列要求：

( 一 ) 考试用试件的坡口表面和坡口两侧各 25mm 范围内应当清理

干净，去除铁屑、氧化皮、油、锈和污垢等杂物。

(二 )焊条和焊剂应当按规定要求烘干，随用随取，焊丝应当除油、

除锈。

( 三 ) 焊工、焊接操作工应当按照评定合格的焊接工艺规程焊接考

试试件。

( 四 ) 操作技能考试前，应当在考核中心成员、监考人员与焊工或

者焊接操作工共同在场确认的情况下，在试件上标注焊工或者焊接操作

工考试编号。

( 五 ) 水平固定试件和 45°固定试件上应当标注焊接位置的钟点标

记，定位焊缝不得在“6 点”标记处；管材向下焊试件应当按照钟点标

记固定试件位置，且只能从“12 点”标记处起弧，“6点”标记处收弧；

向上焊时应当从“6点”位置起弧。

( 六 ) 焊工的所有考试试件，第一层焊缝中至少应当有一个停弧再

焊接头；焊接操作工考试时，每一焊道中间不得停弧。

( 七 ) 机械化焊接考试时，允许加引弧板和引出板。

( 八 ) 试件开始焊接后，焊接位置不得改变；对于管材对接和管板

焊缝的 45°固定试件，管轴线与水平面间的夹角应当在 45° ±5°范围

内。

( 九 ) 试件表面最后一层不允许修磨和返修。

( 十 ) 试件坡口形式和尺寸应当按照焊接工艺规程制备，或者由考

核中心按照相应国家标准和行业标准制备。

第四章　考试结果评定、证书颁发与管理

第十四条　焊工、焊接操作工基本理论知识和专项理论知识考试均

采用百分制计分，60 分为合格。

第十五条　焊工、焊接操作工操作技能考试通过试件检验进行评定。

考试试件经检验合格后，该考试项目为合格。

第十六条　两名以上焊工、焊接操作工参加组合考试时，如果其中

某考试项目不合格，且能够确定导致该考试项目不合格的施焊焊工或者

焊接操作工的，则应当认定该焊工或者焊接操作工的考试项目不合格；

不能确定导致该考试项目不合格的施焊焊工或者焊接操作工的，则应当

认定参与该组合考试的焊工和焊接操作工均不合格。

第十七条　焊工、焊接操作工操作技能考试不合格的，允许在一个

月内补考一次。补考不合格者可以重新申请考试，但与前次考试的时间

间隔不得少于三个月。

第十八条　考核中心应当将焊工、焊接操作工考试的结果记入考试

评定报告，将操作技能考试试件的检验结果记入考试检验记录表。

考核中心应当在考试结果评定后 10 个工作日内，将考试合格焊工、

焊接操作工的考试评定报告，经中心主任签字并加盖公章后，报国务院

核安全监管部门。

第十九条　民用核安全设备焊工、焊接操作工只能从事考试合格项

目对应范围内的焊接活动。

第二十条　考核中心应当建立并管理焊工、焊接操作工档案，档案

应当包括焊工、焊接操作工连续操作记录等。

焊工、焊接操作工聘用单位应当填写焊工、焊接操作工连续操作记录，

并每六个月报相关考核中心备案。

第二十一条　国务院核安全监管部门应当自收到考试评定报告之日

起 20 个工作日内，完成对焊工、焊接操作工考试结果的审查，并作出是

否授予资格的决定。

国务院核安全监管部门应当自作出决定之日起 10 个工作日内，向考

试合格的焊工、焊接操作工颁发资格证书。

第二十二条　焊工、焊接操作工资格证书应当包括下列主要内容：

( 一 ) 焊工、焊接操作工姓名及聘用单位；

( 二 ) 考试合格项目；

( 三 ) 有效期限；

67 HAF 证书

( 四 ) 证书编号。

第二十三条　民用核安全设备焊工、焊接操作工不得同时在两个以

上单位中执业。

持证焊工、焊接操作工变更聘用单位的，应当由聘用单位向考核中

心提出资格证书变更申请，同时应当提供原聘用单位的意见，经国务院

核安全监管部门审查同意后更换新的资格证书。更新后的证书有效期适

用原证书的有效期。

第二十四条　焊工、焊接操作工资格证书的有效期限为 3年。

资格证书有效期届满，在有效期内从事考试合格项目的焊接工作质

量优良，需要继续从事焊接活动的持证焊工、焊接操作工，应当于有效

期届满 60 个工作日前，向考核中心提出延续申请。

考核中心应当自收到延续申请之日起 10 个工作日内，完成延续申请

的初步审查，提出是否准予延续的建议，并将延续申请和焊工、焊接操

作工连续操作记录报国务院核安全监管部门审查。

国务院核安全监管部门应当在焊工、焊接操作工资格证书有效期届

满前，作出是否准予延续的决定。准予延续的，可以延长一次，延长期

限为十二个月，延长期自焊工、焊接操作工考试合格项目有效截止日期

算起。

不符合延期条件或者延长期满的焊工、焊接操作工，需要继续从事

焊接工作的，可以重新提出申请。

第二十五条　连续中断焊接工作超过三个月的，焊工、焊接操作工

所持资格证书自动失效。

连续中断考试合格项目对应的焊接工作超过六个月的，焊工、焊接

操作工所持资格证书中的相应考试项目的合格记录自动失效。

第二十六条　考试评定报告和焊工、焊接操作工资格证书中操作技

能考试的合格项目应当用代号表示。代号的组合顺序为焊接方法分类号、

试件形式代号、焊缝形式代号、母材类别号、焊接材料、试件规格尺寸、

焊接位置代号、焊接要素分类号。

第二十七条　取得国外相关资质的境外单位焊工、焊接操作工，经

国务院核安全监管部门核准后，方可在中华人民共和国境内从事民用核

安全设备焊接活动。

第二十八条　民用核安全设备焊工、焊接操作工有舞弊行为的，由

考核中心取消其考试资格，并停考 1年。

第五章　监督检查

第二十九条　考核中心应当在进行焊工、焊接操作工考试 10 个工作

日前，将考试计划、内容和地点书面通知国务院核安全监管部门。

第三十条　国务院核安全监管部门对考核中心的焊工、焊接操作工

考核和管理工作进行监督检查。

监督检查分为综合性检查和专项检查：

( 一 ) 综合性检查内容包括考核中心质量保证体系的运行、人员师

资力量、考核管理制度和细则、考核活动的相关文件和记录、考核计划

及实施等。

( 二 ) 专项检查内容是对考核中心焊工、焊接操作工考核活动的抽

查。

第三十一条　考核中心应当配合国务院核安全监管部门的监督检查，

如实反映情况，提供必要的材料，不得拒绝和阻碍。

第六章　法律责任

第三十二条　考核中心有下列情形之一，由国务院核安全监管部门

责令限期整改；情节严重的，停止其资格考核工作：

( 一 ) 考核中心条件变化，不满足规定要求的；

( 二 ) 不依据本规定进行焊工、焊接操作工考试的；

( 三 ) 拒绝或者妨碍国务院核安全监管部门监督检查的；

( 四 ) 工作管理混乱，考试工作质量低劣的；

( 五 ) 严重违规，弄虚作假的。

第三十三条　从事焊工、焊接操作工资格考核的工作人员，有下列

行为之一，由考核中心停止其资格考核工作，并依据有关法律法规予以

处罚：

( 一 ) 泄露考试内容的；

( 二 ) 考试过程中有徇私舞弊行为的；

( 三 ) 玩忽职守，导致考场纪律混乱，考试结果失实的；

( 四 ) 有其他严重影响资格考试公正性行为的。

第三十四条　民用核安全设备制造、安装单位或者民用核设施营运

单位提供虚假证明的，由国务院核安全监管部门处 1 万元以上 3 万元以

下罚款。

第三十五条　民用核安全设备焊工、焊接操作工超出考试合格项目

范围从事焊接活动的，由国务院核安全监管部门责令其停止民用核安全

设备焊接活动，并依据《民用核安全设备监督管理条例》第四十九条的

规定对聘用单位予以处罚。

第三十六条　伪造、变造民用核安全设备焊工、焊接操作工资格证

书的，依据《中华人民共和国治安管理处罚法》第五十二条的规定，处

10 日以上 15 日以下拘留，可以并处 1000 元以下罚款；情节较轻的，处

5日以上 10 日以下拘留，可以并处 500 元以下罚款。

第三十七条　民用核安全设备焊工、焊接操作工违反操作规程，导

致严重焊接质量问题的，由国务院核安全监管部门吊销其资格证书。

第七章　附　则

第三十八条　本规定以外的焊接方法、材料种类的焊工、焊接操作

工考试，其内容、方法和评定标准由企业和考核中心按照有关产品设计

和制造技术条件制订，并报国务院核安全监管部门备案。

第三十九条　本规定自 2008 年 1 月 1 日起施行。1995 年 6 月 6 日

国家核安全局发布的《民用核承压设备焊工、焊接操作工培训、考试和

取证管理规定 (HAF603)》同时废止。

68 会议展会

北京天津西安

贵州

上海

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这是在美国召开的关于小型模块化反应堆的高层会议。会议聚集了来自美国和其他国家的龙头企业和专家，他们在研发小

型模块化反应堆方面有显著成就。

3个案例分析及发展更新现状：

• 美国巴布科克 & 维尔克斯公司

• 美国西屋公司

• 美国 NuScale Power 公司

发言人名单：

• 美国阿莫林密苏里公司，总裁兼首席执行官， Warner Baxter

• 美国密苏里电气合作协会，首席执行官，Barry Hart

• 美国巴布科克 & 维尔克斯公司，总裁，Christofer Mowry

• 鲍易斯州立大学，经济发展部主席，Geoffrey Black

• 加拿大核安全委员会，高级项目主管，Marcel deVos

• 国际战略研究中心，防扩散项目部主任，Sharon Squassoni

• EXCEL 服务公司，总裁兼首席执行官，Donald Hoffman

• FirstEnergy 核运行公司，法律事务部主任，Greg Halnon

• 燃料循环周刊出版社，发行人，Andrea Jennetta

• 国际原子能机构，水反应堆技术开发部，Mark J. Harper

• 美国 NuScale Power 公司，首席商业运行官，Mike McGough

• ( 美国 ) 橡树岭国家实验室，著名研发人员，Randy Beatty

• 顺德伦国际律师事务所，合作伙伴，Mark Herlach

• 美国田纳西河流域管理局，小型模块反应堆技术高级经理，Daniel Stout

• 美国核管理委员会，小型反应堆审批二部，部长，Anna Bradford

• 美国能源部，副助理部长，Edward McGinnis

• 美国能源部，副助理部长，John Kelly

• 美国能源部，先进反应堆实验室，Craig Welling

• Ux 咨询服务公司，国际高级副总裁，Jonathan Hinze

• 西屋电气公司，首席技术官，Kate Jackson

想了解更多确切信息，请登陆网站：www.platts.com/smallmodularreactors

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基准测试：回转炉拆除活动分析作者：Mitsuo TACHIBANA, Sari IZUMO, Noritake SUGITSUE, Seung-Kook PARK

日本原子能机构： [email protected]

韩国原子能研究院：[email protected]

介绍

2008 年日本原子能机构 (JAEA) 与韩国原子能研究院 (KAERI) 就核能

源和平应用签署了合作协议。协议中包含了核设施的拆除和退役 ( 又称

D&D)。根据协议规定，两个机构每年定期召开 D&D 活动技术交流会。

每个机构都有铀转换设施 ( 又称 CF)。JAEA 拥有铀提炼和转换工厂 (

简称为 URCP 厂 )，KAERI 也拥有一家铀转换工厂 ( 简称为 UCP 厂 )。这些

设备在最终完成所有的转换工作后都会退役。这两家机构均配备退役工程

系统，不仅可以制定退役计划，而且能够有效的进行设备拆除活动。JAEA

的退役系统全称是核设施退役工程系统 ( 简称 DENESYS)，KAERI 的系统是

退役工程系统 (简称 DES)。

为了验证两家机构的交互退役工程系统，JAEA 和 KAERI 联手展开了基

准测试。

首先，两家机构各自就交互退役系统进行比较。其次，每家机构各自

就回转炉拆除的程序、参数及拆除项目的管理数据进行对比。最后，通过

交互退役工程系统对回转炉拆除所需的管理数据进行评估。比如就现在来

讲，在 KAERI 获取的回转炉拆除管理数据是通过 JAEA 的核设施退役工程

系统评估得出的。

本篇报告将会对 JAEA 和 KAERI 的回转炉拆除活动的对比结果及 JAEA

的评估结果展开详细描述。

铀转换拆除和退役活动概述

JAEA 的铀提炼和转换工厂 (URCP 厂 ) 位于日本西部的冈山县人形峠，

KAERI 的铀转换工厂 (UCP 厂 ) 位于韩国中部的大田市。而且这些设备现

在处于退役期。

JAEA 的 URCP 厂拆除与退役

URCP 工厂共有上下三层，建立于 1981 年，其中辐射管制区域面积为

7300m2。该厂有湿性转换设备和干性转换设备。第一种设备负责将铀精矿

转换成 UF6，第二种设备负责将 UO3 转换成 UF6。该厂的运行时间为 1982

年至 1999 年，期间 UF6 的总产量达 750 吨。

URCP 厂的湿性转换设备已于 2000 财年至 2001 财年拆除。(1)2008 年

该厂开始着手进行干性转换设备的拆除活动。(2) 与铀加工相关的设备于

2011 年 9 月实施拆除。流体介质地下存储罐、中和系统、沉淀系统及通

风系统也于 2012 财年开展拆除活动。

拆除活动所产生的废物暂时存放在 URCP 厂，2008 年至 2011 年的设备

拆除总重为 470 吨，其中所需的人力时间总计 12000 个工作日。

KAERI 的 UCP 厂拆除与退役

UCP 工厂共有上下三层，建立于 1982 年，其中辐射管制区域面积为

1981m2。UCP 厂配备重铀酸铵加工设备 ( 简称 ADU 设备 ) 和碳酸铀酰铵加

工设备（简称 AUC 设备）。UCP 厂曾为韩国 Wolsong-1 号 CANDU 反应堆生

产了 100 吨的 UO2 粉末。该厂于 1992 年关闭。(3)

该厂的退役活动于 2004 年正式开展，项目活动包括拆除 UCP 工厂的

所有设备、对工厂建筑内部和金属废物进行净化处理、处理被污染的土壤

和污泥废料、净化泻湖机构，并对工厂做放射最终调查。在退役工程结束

后，该厂的建筑将会重新开放，以作它用。

退役工程已于 2011 年结束。期间产生的放射性金属和混凝土废物总

重 379 吨，可释放性废物达 143 吨。其中所需的人力时间总计 13875 个工

作日。

退役工程系统

每个机构都配备自主研发的退役工程系统。JAEA 的 DENESY 系统在提

供有效信息、制定有效退役计划及实施拆除活动等方面发挥了积极的作用。

KAERI的DES系统也有类似的功能，如提供有效信息、设计并制定退役计划、

许可证获取、步骤制定及拆除程序设置等。

JAEA--DENESYS 系统概述

DENESYS 由四个评估系统构成。分别是拆除项目数据管理评估准则 (

简称 PRODIA 准则 )；拆除项目辐射曝露评估准则 ( 简称 REX 准则 )；核反

应堆退役产生的残余辐射量评估准则 ( 简称 RADO 准则 )；简化的退役成

本评估准则 (简称 DECOST 准则 )。

PRODIA 准则可以根据设备重量、人工消耗量及拆除活动计算出拆除活

动所需的人力总量及产生的废物总重。REX 准则可以评估出公众和员工在

运输经过切割的退役设备中所接受的辐射剂量；RADO 准则可以根据设备

运行年限及材料组成数据等计算出排放的中子废物及带有辐射性的废物总

量等。DECOST 准则根据人力总量和设备重量简单估算出退役活动所需的

成本。

72 科技文章

KAERI-- DES 系统概述

DES 也由四个系统构成。分别是退役设施描述 DB 系统 ( 简称

DEFACS)；退役模型系统 (DEMOS)；退役信息系统 (DECOMMIS) 和退役项目

单位工作率评估体系 (简称 DEWOCS)。

DEWOCS 通过退役项目的单位生产率计算出相关数据，其主要依据来源

于 DECOMMIS 系统和 DEFACS 系统及退役项目产生的实际数据。DEWOCS 系

统产生的数据将用于其它设备的退役计划制定。

DEMOS 系统的主要作用有为新设备的退役提供样板，根据工作特性评

估退役成本及人力消耗总值，计算拆除活动、去污净化及废物管理设备需

消耗的时间及成本，预估项目所需的人力及项目持续时间。DEMOS 系统进

行评估的数据来源于 DEWOCS 系统的评估数据，如退役项目单位工作率、

人工成本、设备成本及退役项目产生的实际数据等。

JAEA 和 KAERI 回转炉拆除程序对比

回转炉是两个机构进行比照的一个参照设备。其中 JAEA 的 URCP 厂的

回转炉用于 UF4 的粉粹和干燥，经过加工的 UF4 具有较高的稳定性，将被

长期储存于200L的圆筒内。KAERI的UCP厂回转炉主要用于重铀酸铵加工。

表 I分别罗列了 JAEA 工厂和 KAERI 工厂的回转炉参数。

用于基准测试的回转炉拆除活动、管理数据的分析结果如下：

表 I. JAEA 厂和 KAERI 厂回转炉相关参数

JAEA--URCP 工厂 KAERI--UCP 工厂

回转炉

名称回转炉 (X-S130) 湿法氟化回转炉 (263-25)

材料 SUS SUS

尺寸 φ500 x 3,950 mm φ268 x 5,840 mm

重量 2,700 kg 3,000 kg

回转炉安装室

名称 UF4 加工室回转炉室 (6210)

尺寸 12.0 x 12.0 x 6.5 m 5.4 x 14.0 x 3.4 m

设备总重 (不包

含管道，阀门及

电缆 ) 14,942 kg 8,519 kg

图一 JAEA 工厂回转炉

JAEA 工厂回转炉拆除程序

如图一所示，回转炉被安装在工厂的 2层，位于 UF4加工间的支架上。

与回转炉相连接的有粉碎机、用于收集粉末的机罩、中间接收器及螺旋加

料器。

拆除程序的第一步是移除回转炉机罩、拆除回转炉和支架。

在进行拆除活动的同时，会建立一个环保隔离室 (GH) 用于存放卸载

的回转炉。GH 只是一个临时建筑，目的是防止项目拆除过程中产生的污

染的传播。该临时房是使用胶带将塑料板粘在管架上建成的。房间的尺寸

是 11.0 x 7.0 x 4.0m。

第二步的是拆除中间接收器和螺旋加料机。在收集完 UF4 粉末后，回

转炉将会经过机械分割。粉碎机和袋滤器也会被拆除。当所有的拆除活动

都完成后，环保隔离室也会被拆掉。

被切碎的设备碎片将会储存在容积为 1M3 的网眼容器内。当工作人员

在 GH 外进行拆除活动时，需戴棉质手套和橡胶手套；当员工在 GH内工作

时，则需佩戴棉质手套、双层橡胶手套、防护服、全罩式面罩。

JAEA工厂拆除的设备重量总计14942kg(不包含管道、阀门及电缆)，

所需的人力工时为 1544.6 小时。

KAERI 工厂回转炉拆除程序

湿法氟化回转炉安装于 UCP 工厂的 2层。

与搅拌床反应器链接的管道、电缆等被安装在回转炉室靠近西侧墙面

的地方，拆除时用电缆剪、切片机或切管机减掉 40cm 电缆，然后将这些

拆除下来的管道、电缆等移送至一个特殊的房间进行净化处理。在移除含

石棉的管道时，操作人员必须佩带半罩式面罩。

GH 是一个封闭的大房间，由若干带缺口的小房间组成，墙面材料使用

的是压克力板和其它材料。GH 位于工厂二层，建筑面积为 1560m2

先将抽取式螺旋、驱动器、二次氧化筒、沉淀器移送至特殊操作间；

然后将可移动机盖、马弗炉及回转炉的炉盖送至特殊操作间。在拆除炉盖

的绝缘体时，操作人员需穿防护服，带半罩式面罩。然后拆除螺旋输送机

的卸料阀，并用旋转式带锯对螺旋输送机进行切割。

大部分设备将会被切割成 40cm，方便净化处理或熔融。不锈钢废物将

会被运送到特殊的操作间，由操作人员用配备超声波清洗剂或蒸汽清洗装

置的化学去污设备对这些废物进行去污处理。碳钢废弃物也会被运送到特

殊的工作间，通过感应熔炼炉进行熔融。

在完成设备的拆除后，操作人员将会用刨床和蒸汽清洗装置对建筑地

板、墙体、天花板等进行净化处理。回转炉室的设备总重达 8519kg，所

需人力时间为 1029 工时。

73 科技文章

JAEA 和 KAERI 回转炉拆除程序的区别

JAEA 厂的回转炉直径是 KAERI 厂回转炉的 2 倍，其 KAERI 回转炉的长

度是 JAEA 设备的 1.5 倍。这两台设备的重量相差不大。JAEA 的回转炉安

装在支架上，距离地面 1.7 米；KAERI 的回转炉安装在水泥台上，距离地

面 0.5 米。

这两家工厂的回转炉在安装和拆除程序上都存在差别。比如，KAERI

工厂的回转炉无需支架，直接安装在地面上，且该厂的环保隔离室 (GH)

建在第 2层，并覆盖本层所有的工作间。

图二 KAERI 工厂回转炉

JAEA 和 KAERI 工厂回转炉拆除的管理数据对比

两家机构的交互退役工程系统收集回转炉拆除活动产生的管理数据，

并对其进行分析。

拆除活动管理数据的分析

JAEA工厂的设备总重量为14942kg ，共计1544.6工时。其中准备工作、

拆除活动及善后工作所需的时间分别为 426.2 工时 , 921.6 工时和 196.8

工时。表 II 为 JAEA 工厂不同拆除项目所需的人力。该厂拆除项目的工作

效率为 9.67kg/ 工时。

KAERI 工厂设备总重量 8519kg，共计 1029 工时。拆除项目的工作效

率为 8.28kg/ 工时。

尽管 JAEA 工厂的回转炉安装在支架上，该厂的拆除效率却高于 KAERI

工厂。下一步我们将对这两家机构的回转炉拆除活动进行细化分析，以找

出其中的区别及其原因。

表 II. JAEA 厂拆除活动所需人力表

工作项目重量 (kg) 人力 (工时 )

控制面板拆除 270 27.8

回转炉、粉碎机、

螺旋加料机拆除 6481 699

气体预热器拆除 130 13.5

收集粉末的机罩拆除 400 44.1

袋滤器、鼓风机、 510 40.5

过滤装置拆除

回转炉支架拆除 6204 31.5

混凝土底座拆除 947 65.3

根据 JAEA 厂 PRODIA 准则评估 KAERI 厂拆除项目的管理数据

KAERI 回转炉室内设备拆除活动产生的数据是依据 JAEA 厂的 PRODIA

准则得出的 (即拆除项目数据管理评估准则 )。(4), (5) 评估系统有效运

行的前提是假设两个工厂采用同样的步骤和方法实施设备拆除。我们假设

的拆除程序如下：

- 首先，对进行设备拆除的工作间进行检测；

- 将工作间的地板用塑料薄膜覆盖；

- 在工作间安装切割设备；

- 将材料和工具运至该工作间；

- 如图三所示，在回转炉室安装环保隔离室；

- 在准备程序完成后，切割需拆除的设备，并将其装在环保隔离室内

的 200L 圆筒内；

- 装满切割碎片的 200L 圆筒被运送至储藏室；

- 将工作间内的材料、工具及切割设备搬出；

- 拆除环保隔离室并清理工作间。

根据 PRODIA 评估准则，拆除 KAERI 厂回转炉室所有设备所需人力时

间为 1294.8 工时。实践证明，根据该准则评估出的时间总数是 KAERI 实

际所需时间的 1.26 倍，其中不包含去污净化活动消耗的人力时间。

结论

为了验证两家机构的交互退役工程系统，JAEA 和 KAERI 联手展开了基

准测试。其中，回转炉被选定为进行基准测试的参照物。测试就两家机构

JAEA 和 KAERI 厂回转炉拆除步骤及产生的管理数据进行比较。测试结果

显示，两家机构回转炉的安装位置及拆除程序都有不同，且 JAEA 的拆除

效率要高于 KAERI。

KAERI 厂回转炉拆除活动所得出的管理数据是根据 JAEA 的 PRODIA 准

则评估得出的。根据该准则评估出的人力消耗时间是 KAERI 实际时间消耗

74 科技文章

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的 1.26 倍。

图三 KAERI 厂设备拆除操作间：环保隔离室

参考资料

1. 《RANDEC 杂志》日语版，2009 年第 39 期，18—29 页；标题：

“人形峠中心 JAEA 厂铀转换设施退役现状”作者：S. Ikegami, Y.

Tsunashima, M. Murata 等。

2. 美国爱达福尔斯 2010 年 DD&R 步骤研讨会（有光盘），8 月 29 日

至 9 月 2 日 , “日本原子能机构铀提炼及转换工厂退役项目”，作者：

N. Takahashi, Y. Morimoto, N. Sugitsue。

3. 美国爱达福尔斯 2010 年 DD&R 步骤研讨会（有光盘），8 月 29 日

至 9 月 2 日 , “铀转换工厂退役项目”，作者：D. S. Hwang, K. I.

Lee, Y. D. Choi 等。

4. 美国亚利桑那州凤凰城，WM2012 步骤研讨会， 2012 年 2 月 26 日

至 3 月 1 日，“铀提炼及转换厂退役项目管理数据评估体系调查研究”，

作者：H. Usui, S. Izumo, Y. Shibahara 等。

5. 2011-010 JAEA 技术研讨会，“FUGEN -2 核电站设备拆除及第 3、

第 4 给水加热器室清理活动人力消耗评估模式的调查研究”，作者：Y.

Shibahara, M. Tachibana, M. Izumi 等。


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项目，不仅能为中国沿海地区的核电发展，还能为全中国，甚至国际提供服务。

据介绍，此前，中核集团已对在国内沿海有关省市近 40 个项目备选厂

址上进行了严格的踏勘和量化评审。最终确定的这一选址，或与邻近的正在

建设的台山核电站有关，这座核电站是中国广东核电集团在该省建设的第四

座核电站。按照规划，到 2020 年，该省的核电站将全部投入生产，一年就

节煤 6000 万吨。

来源：http://www.heneng.net.cn/

我国研制成功第四代核电“快堆”控制棒组件

标签：第四代核电控制棒

“快中子反应堆”简称“快堆”，是我国正在研发的第四代核电事业。

大连博恩坦科技有限公司与中国原子能科学研究院合作，在国内率先实现快

堆关键部件——“控制棒组件”的自主的生产。

大连博恩坦公司 2011 年与中国原子能科学研究院签署合作协议，承担

了我国快堆控制棒的研制和国产化工作。在两年时间里，企业投入 5000 多

万元，与清华大学、天津大学等 13 所科研院所开展合作，先后攻克了材料

分离、导热、膨胀等多个难题。

目前，大连博恩坦公司已在相关领域取得 3 项国家发明专利，并在国内

率先实现硼同位素产品的工业化生产，打破了欧美等少数国家的技术垄断。

据介绍，大连博恩坦公司的硼同位素产品还在军事、光伏、LED 芯片等

领域应用广泛，今年预计实现销售收入 3000 万元。

来源：http://www.china-nea.cn/

中核设计提前完成阳江核电一期 4LX+3.80 风管及支架改版

4 月 10 日，阳江核电一期 4 号机组 4LX+3.80 风管及支架图纸改版完成

并正式发布，较计划提前 431 天实现现场设计分包合同里程碑，这为阳江核

电一期 3、4号机组通风系统安装创造了良好条件。

自阳江项目通风专业现场设计工作全面开展以来，中核设计不断优化工

作流程，针对 3、4 号机组与 1、2 号机组图纸具有相似性这一特点，积极与

上游设计沟通，及时获取 3、4 号机组图纸设计的变化信息，并在细化改版

时重点关注有变化的地方，广泛甄别在 1、2 号机组出现的问题，使得现场

变更量相对 1、2 号机组同期减少了 60% 左右，极大地提高了工作效率，将

服务现场、追求卓越的理念落到实处，充分展现了中核设计的良好形象。


CAP1400 示范工程审评启动会在北京召开

2013 年 4 月 2 日，国家大型先进压水堆核电站重大专项 CAP1400 示范

工程（以下简称“示范工程”）审评启动会在北京召开。本次会议由环境保

护部（国家核安全局）组织，国家核安全局核二司副司长俞军、国家核电技

术公司副总经理孙汉虹、时家林等参加会议。

在启动会上，国家核安全局有关领导重点部署了后续 CAP1400 示范工

程两评报告、PSAR 报告、试验验证等审评工作和进度计划安排，明确了

CAP1400 示范工程 PSAR 阶段试验验证的各项标准和要求。CAP1400 示范工程

将通过一系列严格的安全标准审评，满足国内和国外最先进的核电安全法规

标准要求，成为代表国家创新能力的三代先进压水堆核电机组。

环境保护部核与辐射安全中心、华北核与辐射安全监督站、机械院核安

全与可靠性中心、苏州核安全中心（含中广核设计院）、北京核安全审评中

心（含中国核电工程有限公司）、中国核动力研究设计院、国家核电技术公司、

国核示范电站有限责任公司、上海核工程研究设计院等单位约 200 名领导、

专家和代表参加了会议。

CAP1400 示范工程审评启动会现场来源：中国核电信息网

新闻77


高温气冷堆首次大件吊装任务顺利完成

4 月 14 日，由中国核工业二三建设有限公司负责施工的高温气冷堆首

次大件吊装——屏冷水型模块顺利吊装就位，标志着高温气冷堆蒸发器舱室

-8 米以下屏冷水吊装完成，为项目后续各项工作的开展创造了良好的开端。

此次吊装的两组屏冷水模块均采用 156 根 Φ38（直径为 38 毫米）的钢

管组成，形成尺寸为 7310*7200*7320（单位：毫米）的管束，通过下部联箱

连结。4 月 10 日，中国核工业二三建设有限公司完成两组屏冷水模块的全部

制作；4 月 14 日 6 时，400 吨吊车开始起钩翻转；6 时 45 分，第一组屏冷水

模块顺利吊装就位；8时 30 分，第二组屏冷水模块顺利吊装就位。

来源：http://www.heneng.net.cn

国内首套 CAP1400 核电稳压器锻件成功冶炼浇注

近日，国内首次制造的 CAP1400 核电稳压器锻件在中国第二重型机械集

团公司炼钢车间一次性冶炼浇注成功。

CAP1400 核电稳压器锻件采用国内具有自主知识产权的第三代非能动核

电机组标准，产品化学成份控制要求严格，无损探伤和力学性能等各项指标

要求高，是目前生产冶炼难度最大的产品之一。其冶炼工序必须要彻底脱磷、

脱硫、脱气、去除杂质，还要精确控制化学成份，最大限度地提高钢锭的纯

净度，确保产品质量。

二重对原材料准备情况、生产设备状况及拟采取的相关措施进行了充分

准备。冶炼浇注过程中，严格控制磷含量，精确控制化学成份，提高钢液纯

净度；同时，还精心控制注温注速，切实做到了精心准备、精心冶炼、精心

浇注，确保了化学成份等冶炼技术参数完全符合工艺要求。

来源：http://www.cnnc.com.cn

哈电研制中国首台自主百万千瓦级核主泵电机成功发运

4 月 8 日，哈电集团研制的中国首台具有自主知识权的方家山核电工程

核主泵电机成功发运，标志着我国已打破主泵组技术长期被欧美等国家垄断

的局面。

据出厂试验数据表明，电机的各项性能指标完全符合设计要求，达到了

国际先进水平。据了解，方家山核电工程是秦山一期核电工程的扩建项目，

规划建设 2 台 100 万千瓦级压水堆核电机组，采用二代改进型压水堆技术。

哈电集团与奥地利安德里茨公司联合中标，共计获得 2 套机组的 6 台核主泵

组。其中，电机采用轴封式设计，由哈电集团负责研制。

来源：http://www.china-nea.cn

中国自主三代核电 ACP1000 通过鉴定达国际水平

据《经济日报》报道，中国核工业集团公司自主研发的具备完整自主知

识产权的先进压水堆核电站 ACP1000 初步设计通过了国家核行业权威鉴定。

专家一致认为，ACP1000 的技术和安全指标达到了国际上三代核电机组的同

等水平，设计、建造能够完全实现自主化。

据介绍，ACP1000的开发是中国核工业集团公司在中国30余年核电科研、

设计、制造、建设和运行经验的基础上，充分借鉴国际三代核电技术先进理念，

汲取福岛核事故经验和教训，满足国际最先进的法规标准。ACP1000 拥有良

好的核电自主化和国产化基础，有丰富的建造和运行经验可以借鉴，具有较

大的经济优势。


天威中标我国西部首个核电站项目河北保定天威保变电气股份有限公司日前成功中标我国新一轮西部大开

发标志性工程中广核广西防城港核电站一期工程 2×1000MW 机组配套使用的

7台 400MVA/500kV 单相升压主变压器。

防城港核电站是我国在西部地区和少数民族地区开工建设的首个核电

项目。一期工程建设两台单机容量为 108 万千瓦的压水堆核电机组，计划

2015 年初第一台机组建成投入商业运营。


L-3 MAPPS 恩巴尔塞全范围仿真机整装待发2013 年 4 月 25 日，L-3 MAPPS 在蒙特利尔市宣布其为阿根廷核电公司

（NA-SA）开发研制的恩巴尔塞全范围仿真机于 2013 年 3 月 22 日在恩巴尔

塞核电站中投入使用，该核电站位于阿根廷科尔多瓦省紧邻恩巴尔塞的里奥

特赛罗小城的一个水库南岸。当日，L-3 MAPPS 与 NA-SA 公司齐聚在科尔多

瓦来庆祝这一重大的成功，此次项目被称作“整装待发”。

恩巴尔塞仿真机将会为恩巴尔塞核电站单一机组的增强型操作培训提供

保障，其单一机组采用净输出为 600 兆瓦的 CANDU-6 重水堆，该反应堆并于

1984 年 1 月 20 日投入商运。L-3 MAPPS 最近研制的一个全范围 CANDU 核电

仿真机是专门为位于中国浙江省的秦山核电站三期工程设计的，该核电站于

2003 年第一个季度投入运营。自此，L-3 MAPPS 为核能行业引入了众多关键

技术，包括在 L-3 Orchid® 模拟情境下开发的电站模型、冗余电站计算机模

拟系统与高度先进的紧凑型输入 / 输出系统，上述所有技术全部应用在生产

顶尖的恩巴尔塞仿真机上。

L-3 MAPPS电力系统和仿真市场营销副总裁，Michael Chatlani说：“通

过努力研发并采用当今最新的软硬件技术及仿真技术，L-3 生产了最具现代

化的全范围 CANDU 核电仿真机，这个项目对于 L-3 MAPPS 来说至关重要，因

为它使我们成为唯一有资格开发新一代 CANDU 核电仿真机的制造商。我们非

常感谢 NA-SA 公司提供给我们的合作机会。”

“随着恩巴尔塞全范围仿真机投入使用，首个核电站寿命延长项目

的交付成果已成功实现。NA-SA 公司核电站寿命延长项目负责人，Rubén

Semmoloni 表示：“对于 L-3 MAPPS 和 NA-SA 技术团队在生产仿真机过程中

所表现出的合作与创新精神，我们对其报以热烈的掌声，这将成为未来 25

年中我公司安全文化和人员培训的核心环节。”

恩巴尔塞全范围仿真机采用 L-3 领先的 Orchid 模拟环境，在个人计算

机的 Windows 系统上运行。所有核电站的模拟系统都是在 Orchid 模拟环境

下开发、验证与维护的，包括反应堆、核蒸汽供应系统、核电平衡系统、电

气系统和仪控系统。全范围仿真机的核电计算机系统（又称为数字控制计算

机 DCCs）采用的是全范围模拟双核 DCC 系统。

78 科技文章

新闻79

企业新闻中核中石化“联盟”成立铀资源勘查开发公司

3 月 29 日，中核集团地矿事业部与中石化华北分公司在京签署了“中

核石化铀业有限公司”合资协议。协议的签署是对两大集团战略合作协议的

具体落实，标志着两集团在铀资源勘查开发方面的合作将进入实质阶段。地

矿事业部主任杜运斌与华北石油局局长周荔青代表双方签署了协议。

中核石化铀业有限公司被定位为中核集团与中石化集团铀资源勘查开发

的合作平台，由中核集团控股。双方将发挥各自优势，以内蒙古柴登地区项

目为切入点，逐步拓展合作领域和范围，互惠共赢，携手打造中央企业合作

的典范。

来源：http://news.bjx.com.cn/

中核集团投资建设“一站式”核燃料加工产业链

3 月 31 日，中核集团龙湾工业园项目合作协议签字仪式在京举行。中

国核燃料总公司与广东省鹤山市共同签署了《中核集团龙湾工业园项目投资

框架协议书》、《中核集团龙湾工业园项目用地协议书》。根据国家核电发

展规划和中核集团核燃料产业发展战略，中核集团将在广东省江门市投资建

设龙湾工业园，打造“一站式”服务核燃料加工产业链，集中建设铀纯化转化、

铀浓缩、核燃料元件制造等设施。

按照项目规划，2020年前建成国际一流的核燃料加工产业集群，形成“合

作、共赢”的核燃料加工管理经营体制，逐步成为具有标志性的亚洲核燃料

加工中心。这是中核集团着眼于国内核电发展和国际核能产业发展，优化资

源配置，提升产业发展核心竞争力，实现现有核燃料产业转型升级和跨越式

发展的重大举措，对国家核电行业和核燃料产业的发展具有重要意义。

中核集团董事长、党组书记孙勤，总经理、党组副书记钱智民，党组成

员、副总经理杨长利，国防科工局系统二司副司长吕晓明，广东江门市委书

记刘海，副市长吴国杰，鹤山市市委书记郭伟，中国广东核电集团有限公司

总经理助理刘开新等出席了签字仪式。

孙勤在签字仪式前举行的座谈会上表示，龙湾工业园项目具有安全、高

效、现代企业管理模式等特点，不仅能为中国沿海地区，还能为全中国，甚

至国际提供服务。作为一个资金密集、技术密集、人才密集，效益密集的项目，

希望江门市市委、市政府给予关心和大力支持，并做好社会风险评估和科普

宣传。

钱智民在签字仪式上说，龙湾工业园项目涉及核燃料供应、核能清洁能

源建设、能源结构调整、环境改善等，建好该项目就是实实在在为建设“美

丽中国”做贡献。他表示，中核集团以及核燃料公司将认真落实集团公司董

事会相关要求，一步步向前推进工作，尽快促使项目开工，按照国际标准尽

快圆满建成。

刘海在致辞中表示，将继续要求鹤山市全面落实项目所有准备工作；在

项目落地后，将全力做好后勤保障。他希望，协议签署以后，双方能按照工

作目标协同工作作战，把任务完成好。

据了解，中核集团高度重视核燃料产业园建设。2012 年 2 月，中核集

团总经理办公会审议通过了核燃料产业园区规划及建设方案，成立了由中核

集团领导亲自挂帅的核燃料产业园建设领导小组和工作组，组织专业人员在

国内沿海有关省市近 40 个项目备选厂址上进行了严格的踏勘和量化评审，

根据规划和厂址评选择优原则，最终确定在广东省江门市鹤山市址山镇大营

工业园区选址建设龙湾工业园。


山东台海全资购法核电企业三代半装备全球唯一

莱山区核电装备产业园又迎来新成员：由意大利卡尔维集团投资 5000

万欧元的卡尔维钛合金项目，在园区正式规划建设。自此，以核电装备制造

企业台海集团领军的这家产业园，已聚集了 20 余家“核”字头企业。

由此，莱山区走出一条独具特色的调结构之路：支持龙头企业利用金融

危机带来的契机，到欧美国家低成本并购先进企业，以此提升自身技术和实

力，在此基础上以龙头企业带动建立产业园，聚集高端新兴产业。

台海集团是莱山区一家民营核电装备制造企业，自建立以来发展十分迅

猛。受金融危机等影响，近年来欧洲许多核电企业经营困难，为低价并购提

供了契机。台海集团抓住这一机会，在区委、区政府支持下，在 2012 年全

资收购世界一流核电设备制造商——法国玛努尔集团，将其 8 家企业全部收

归旗下。台海由此一举成为全球唯一的三代半核电设备生产商，也是目前国

内唯一一家经欧盟许可的核电设备生产企业，在全球核电管道专项设备市场

占有很大份额。

莱山区及时以台海为龙头，规划建设了 7 平方公里的核电产业园。产业

园以商招商，围绕台海生产核电设备所需要的钛合金材料、空气制冷、核尘

净化等上下游配套产品，引来了意大利卡尔维等世界知名企业，形成一个完

整的产业集群。这些企业不仅为台海服务，还将业务扩展到国内外。由此，

莱山打破了国内外许多地方围绕核电站建立核电产业的惯例，以一次海外并

新闻 80

购培育起了一个新兴产业。

据介绍，预计 3-5 年后，台海集团将实现营业收入 100 亿元，将发挥更

大的带动能力。目前在核电装备制造等产业的推动下，莱山区的产业结构正

向“外 ( 外向型 )、高 ( 高科技 )、新 ( 新兴产业 )、绿 ( 绿色产业 )”的特

色迈进。

莱山区委书记金志海十分看重企业海外并购带来的利好。他说，由于产

业发展基础好，莱山区大企业多、高端企业多，具有海外并购的实力。这是

莱山区调结构的一大优势、一条捷径。今后区里将积极复制核电装备产业的

经验，在石油装备、生物医药、节能环保等产业，推动有实力的企业“走出去”

进行并购，以此提升企业水平，提升全区产业结构。

来源：http://www.china-nea.cn/

我国自主研发的核电站 DCS 系统投入应用

日前，福建宁德核电站一期 1 号机组正式投入商运，这是国内首台采用

HOLLiAS-N 核电站 DCS 系统的百万千瓦核电站机组，标志着北京和利时系统

工程有限公司自主研发的百万千瓦级核电站 DCS 系统正式投入应用，打破了

国际知名 DCS 厂家对我国核电控制领域的行业垄断地位。

记者从北京和利时公司了解到，HOLLiAS-N 核电站 DCS 系统是该公司针

对百万千瓦级核电站而定制开发的高端 DCS系统，是核电非安全级 DCS产品。

这套系统从2006年开始启动研发，至今历时7年。目前已应用于红沿河、宁德、

阳江、防城港等多个核电项目中。


中国核电与中核控股开启核能服务战略合作

为进一步促进中核集团核电运营专业化、降低核电运营成本，提升核电

产业服务核心竞争力，中国核能电力股份有限公司与中国中核宝原资产控股

公司于 4 月 15 日在京签署了核能产业服务战略合作框架协议。此次协议的

签订标志着中国核电与中核控股在核电产业服务领域的战略合作正式开始。

双方将基于中核集团总体战略，本着“优势互补、共同发展、互惠互利、合

作共赢”的宗旨，通过业务领域的对接以及商业模式的创新与推广，建立长

期战略合作伙伴关系。中核集团党组成员、副总经理邱建刚，中国核电总经

理陈桦出席签字仪式。

在签字仪式前的座谈会上，邱建刚指出，此次合同的签订对核能产业服

务起步意义重大，是完善核工业服务业的一项重要内容。他希望中核控股能

够搭建完善具有资质的多层次服务平台，提供优质服务，同时也希望中国核

电能够给予支持和帮助。陈桦希望通过此次合作实践，使中国核电业务水平

得到提升，成本得到控制。　

根据协议内容，中国核电与中核控股将共同推动技术支持服务项目在核

电运营产业的应用。双方还将成立核电产业服务推进工作小组，定期举办核

电产业服务对接交流会，指导、协调各自成员单位开展核电产业服务合作推

进工作。


大唐发电参股宁德核电正式运营

大唐发电进入核电领域迈出关键一步，其参股的福建宁德核电有限公司

1 号机组（108.9 万千瓦）4 月 15 日完成 168 小时满负荷试运行并正式投入

商业运行。

宁德核电项目规划总装机容量为 6 台 100 万千瓦级机组，一期在建工程

为 4 台 100 万千瓦级机组。宁德核电股权比例为大唐发电持股的 44%，广东

核电投资有限公司持股 46%，福建省能源集团有限责任公司持股 10%。

大唐发电称，宁德核电 1 号机组的投产是公司进入核电领域的关键里程

碑。宁德核电是国内第一座岛链上的核电站同时也是国内百万千瓦级机组国

产化率最高的核电站。宁德核电机组的陆续投产不仅增加了公司权益装机容

量，预期将给公司带来稳定的利润贡献，推动公司可持续发展；同时对于优

化公司电源结构、保护生态环境，都具有重要意义。

来源：http://np.chinapower.com.cn

中达特钢获全市首张核级生产许可证

浙江中达特钢股份有限公司日前收到了国家核安全局颁发的《民用核安

全设备制造许可证》，成为嘉兴市首家获得核级生产许可证的核电关联企业。

中达特钢主要生产锅炉、热交换器用不锈钢无缝管等产品，1998 年获

得“非核级不锈钢管道合格供应商”证书。2010 年 8 月，中达特钢向国家核

安全局递交了民用核安全机械设备制造许可证的申请，经过多次整改试验，

在质量保证能力、人员配置、厂房设施和技术储备等方面获得国家核安全局

认可，被认定在所申请的民用核安全机械设备制造方面具备了《民用核安全

设备监督管理条例》第十三条及《民用核安全设备设计制造安装和无损检验

监督管理规定》第八条所要求的各项能力。


柳工欧维姆迈向第三代核电进军国外市场

2013 年 3 月底至 4 月初，国内著名的三家钢绞线厂家相关人员、中国

　　中核集团龙湾工业园项目合作签字仪式

　　来源：中国核能行业协会

新闻81

核电工程有限公司相关领导、专家以及国家建筑工程质量监督检验中心相关

人员齐聚在柳州，共同见证了柳工欧维姆公司为第三代核电开发的 CP1000

核电用预应力锚固体系型式试验，试验结果表明，该体系各项性能指标均满

足相关标准要求，此次试验的成功为柳工欧维姆公司核电产品迈向第三代核

电打下了坚实的基础。

2008 年 3月，柳工欧维姆公司经过多年的努力终于成功进入核电领域，

公司开发的 K 系列锚具以及配套的张拉、管道成型加工等设备已在 7 个核电

项目上成功应用，但这些核电项目所采用的是二代改进型技术，2011 年日本

福岛核电事故后，各国对核电的安全性更加重视，我国核电在停止一年多的

审批后，于 2012 年 10 月重启，重启后提出了以后新建核电项目采用第三代

核电技术的要求。

第三代核电技术与二代改进型技术有较大的区别，目前国内核电已有田

湾核电、三门核电以及台山核电采用第三代核电技术，这些技术分属不同的

国家：田湾核电采用的是俄罗斯核电技术、三门核电采用的是美国核电技术、

台山核电采用的是法国核电技术。美国第三代核电技术 AP1000 未采用预应

力混凝土，俄罗斯和法国第三代核电安全壳均采用预应力混凝土，预应力系

统都采用 55 孔锚具。

作为核大国，我国也在积极开发自己的第三代核电技术，经过多年的努

力，我国第三代核电 ACP1000 已通过各种评审、设计，计划于 2013 年年底

在福清核电三期工程上首次采用，ACP1000 采用的锚具经过多次变更，最终

确定采用 55 孔锚具。柳工欧维姆公司开发的 CP1000 核电用预应力锚固体系

是为 ACP1000 配套开发的，同时该体系也满足俄罗斯和法国第三代核电技术

的使用要求，在开发过程中得到中国核电工程有限公司的大力支持和帮助。

ACP1000 作为我国有自主知识产权的核电技术，将是我国以后大力推

广的一种技术，也是我国核电出口的主要技术。目前，巴基斯坦、阿根廷等

国已有引进该技术的意向。


200 吨级 " 难成形零件成形机 " 研制成功将用于核电

4 月 18 日 , 在第 10 届宁波紧固件、弹簧及制造装备展览会上，一台打

着“欲与世界一流试比高”的机器非常吸引人眼球。这台机器一边“吃进”

钢材，一边“吐出”螺丝，每分钟能吐 280 只，而最先进的德国机器也只能

吐 240 只。参会人员都十分好奇，纷纷围紧固件行业中的“中国速度”。

谁能想到，生产出“中国速度”的宁波思进机械股份有限公司，5 年前

只是一家没有自主产品的配角企业。科技创新转型升级后，在短时间内，爆

发出惊人能量。下个月，全国第一台 200 吨级“难成形零件成形机”将出厂。

由这台机器制造出来的螺丝将被装在飞机、高铁、核电设备上。

思进机械创办于 1995 年，在高新技术企业密集的宁波国家高新区，思

进机械并不知名。企业创始人、董事长李忠明说：“初创时企业很小，女儿

名字中有‘思’字，希望她长大时，企业也有进一步成长，于是取名‘思进’。

现在宁波提三思三创，讲思进思变思发展，这倒与企业的发展轨迹暗合。”

在长达10年的时间里，这家企业一直给宁波一家知名塑机企业做配套，

公司产值从没有突破过 5000 万元。

2006 年，45岁的李忠明想着企业转型。在师傅的指点下，决定生产“冷

镦机”。冷镦机是用来生产各类标准件、紧固件、异形件的机器，钢材不用加热，

直接放到冷镦机里，就会“吐”出螺丝、螺栓等。

李忠明说，当时宁波国家高新区管委会刚好引进浙江大学、上海交通大

学等科研力量，与企业对接。“一开始他们没看上我，但他们提出的所有科

研要求，我都统统满足，我的诚意打动了他们。”

2008年，李忠明一举淘汰掉50多台效率低、加工精度和质量不高的设备，

购置了新的数控机床。当年的技改投入资金达到 2000 多万元。

2012 年初，思进机械联合浙江大学、上海交通大学进行“难成形零件

成形机”攻关。一年后，这台重达 200 吨的庞然大物在思进的车间诞生。下

个月，这台机器就要出厂，价格只有国外同类产品的五分之一。


国际合作中广核核电运营公司向美国核电同行取经

为更好地拓宽外部技术支持和经验反馈途径，近日中广核集团核电运营

事业部、中广核核电运营有限公司总经理苏圣兵一行访问了美国核电运行研

究所（INPO）、电力研究院（EPRI）和 EXELON 电力公司，就关于未来合作

的方向及领域进行了深入的交流。

在美国电力研究院（EPRI）的夏洛特中心，苏圣兵代表中广核集团公司

运营事业部与其核电维修中心（NMAC）签署了会员协议。本次协议的签署，

意味着从此中广核集团下属的各核电基地及公司各业务中心可以共享 NMAC

的技术成果和经验，提高设备维护技术和工艺水平。


顾军总经理会见瑞士电力高级代表团

2013 年 4 月 9 日，瑞士阿尔匹克能源控股集团（ALPIQ）董事长施韦策

卡特先生（Mr. Hans Schweickardt）率瑞士电力高级代表团到访国家核电

技术公司。公司总经理顾军、专家委副主任孙昌基、首席信息官郭宏波等会

见了来访一行。

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并就中美出口管制合作、参与 2014 年核安全峰会、继续举行中美俄三方专

家研讨等问题交换意见。

鲁培军副署长就继续深化中美合作提出三点建议：一是继续加强中美“特

大型港口计划”项目合作，不断拓宽、充实合作内容，提高合作实效；二是

稳步推进中美合建中国海关辐射探测培训中心项目的各项工作；三是加快磋

商新的中美关于防范核材料及其他放射性物质非法贩运的谅解备忘录。


法中电力协会考察台山寻核电合作伙伴

4 月 11日，法中电力协会成员一行到访台山，考察台山投资软硬环境，

寻求双方进一步合作发展。

12 日上午，法中电力协会成员一行参观了台城高新区冠荣冠立公司，

听取该公司的概况及产品的介绍。随后，成员一行到工业新城参观，并了解

园区内由法国企业投资的安施备核电装备有限公司施工进展情况。

在随后的交流会上，工业新城工作人员向法中电力协会成员一行介绍了

园区的规划和前景。据了解，台山新建的这个工业园是广东省重点产业转移

工业园，属于省推进核电装备产业发展定点园区，也是与中广核集团签订合

作框架协议的核电装备产业园。园区内有国家机械装备检测重点实验室的检

测科研创新平台。

通过现场考察，法中电力协会成员表示，他们正在寻找核电设备合作伙

伴，对园区的检测实验室项目也有兴趣，希望能进一步加强沟通与合作。同

时，他们还就园区投资环境、厂房配套等问题作出提问，并得到相应的解答。

而在当晚的欢迎会上，台山市长张磊出席并对法中电力协会成员们的来访表

示欢迎，他希望法国企业在台山能够生根发芽。


中核集团董事长孙勤会见俄罗斯国家原子能集团副总经理一行

4 月 22 日，中核集团董事长孙勤会见了俄罗斯国家原子能集团公司副

总经理科马洛夫一行。孙勤向科马洛夫介绍了合作建设的田湾核电站二期进

展情况，重申了中核集团与俄罗斯国家原子能集团公司战略合作伙伴关系的

定位。科马洛夫转达了总经理基里延科对孙勤的问候，表示愿在互利共赢的

基础上发展两国在核能领域的全面合作。

双方对中俄在核能领域多年合作，并取得显著成果表示满意，对未来扩

大并深化合作充满信心。集团公司副总经理俞培根与俄罗斯驻华使馆官员等

参加了会见。

来源：http://np.chinapower.com.cn

我公司向瑞士电力高级代表团介绍了公司概况、三代核电自主化依托项

目以及国家大型先进压水堆 CAP1400 进展情况。双方认可发展核电是未来解

决能源需求和二氧化碳减排的最佳选择。

此瑞士电力高级代表团成员来自瑞士和欧洲的电力企业（包括 ALPIQ

集团、AXPO 控股集团、BKW/FMB 能源公司、瑞士电力公用事业联合会和苏黎

世联邦理工学院），旨在调研我国核电尤其是先进型反应堆研发、建设和未

来发展情况。


王炳华董事长谈中美核电合作

2013年 4月 13日下午，由中国产业海外发展和规划协会（以下简称“海

外协会”）和中美能源合作项目（以下简称“ECP”）共同主办的中美能源

合作对话会议在北京召开。美国新任国务卿克里、中国国务委员杨洁篪出席

会议并致辞。国家发展改革委副主任、国家能源局局长吴新雄、中国产业海

外发展和规划协会会长张国宝、外交部副部长翟隽、商务部副部长王超、美

国驻华大使骆家辉、美国贸易发展署署长扎克等出席会议。国家核电技术公

司董事长王炳华参加了会议，并在“清洁能源行业发展与中美双边合作对话”

中发言。

王炳华介绍了目前中美两国之间最大的能源技术合作项目——我国三代

核电自主化依托项目世界首批 4 台 AP1000 机组建设进展情况。他指出，中

美两国企业通过有效的合作，共同走在了全球第三代核电技术创新和应用的

前列，在此过程中，两国核能企业形成了深厚的合作基础和长期的合作意愿。

王炳华从企业的角度，就深化中美核电合作，分享了自己的思考。他认为，

目前，中美两国核能企业以 AP1000 项目建设合作为起点，不断拓展和深化，

在相互提供技术咨询和支持、联合开发新型反应堆、组建合资企业、共建全

球供应链、推进工业标准接轨、联合开发国际市场、联合开展国际投资以及

相互之间的战略投资等方面，已经开展了实际合作或者达成了合作共识，当

前及未来的一系列合作，将有助于双方企业加快技术创新，提升包括中美在

内的全球核电市场的竞争力。

王炳华希望未来两国政府在开放高技术管制、境外投资审批、开发第三

方市场、加强核安全监管、行业资格认证、保证核燃料供应等方面提供更多

的政策支持，并在政府与企业之间建立更为有效的沟通协商机制，以使更安

全、更环保、更经济的核能造福人类。


海关总署副署长会见美国能源部国家核安全署副署长

4 月 16 日海关总署副署长鲁培军在署会见美国能源部国家核安全署副

署长安哈林顿女士，双方积极评价中国海关总署和美国能源部的合作成果，

新闻83

新闻 84

中核集团与阿根廷核电集团交流合作

4 月 22 日，中核集团副总经理吕华祥与阿根廷核电集团董事

R.Quintana 共同主持召开了核电合作第一次高层协调会。双方就关心的议题

进行了坦诚友好的交流，并就相关内容形成了共识。双方表示对未来核电合

作充满了信心。同日，吕华祥还参加了国家能源局核电司司长郝卫平与阿根

廷核电集团代表团的会谈活动。


中广核海外最大投资项目开工将开采非洲铀矿

中国广东核电集团所属纳米比亚湖山铀矿项目近日开工。据悉，这是中

纳两国间规模最大的合作项目，投产后，将使纳米比亚出口增长 20%，GDP

增长 5%。

纳米比亚湖山铀矿项目是目前中国在非洲最大的矿业投资项目。该矿为

近 10 年来非洲乃至世界铀资源勘查领域的重大发现之一，铀矿资源储量位

列世界第三。湖山铀矿项目投产后将成为全球第二大铀矿山，生产总量可保

证 20 台百万千瓦级核电机组近 40 年的天然铀需求。　


L-3 MAPPS 为岭澳核电二期仿真机引入MAAP5 严重事故仿真模型

2013 年 5 月 6 日，L-3 MAPPS 在蒙特利尔市宣布其获得了大亚湾核电运

营管理公司（DNMC）的更新合同，将会为岭澳核电二期工程的全范围仿真机

配备严重事故仿真模型系统，模拟退役情况并对员工进行培训。此次项目凸

显了 L-3 MAPPS 对大亚湾核电公司一如既往的承诺，该项目将立即启动并预

计在 2014 年初投入服务。

“自 2011 年福岛核事故以来，我们可以看到客户对核电严重事故实时

培训仿真机的需求在不断增加”。L-3 MAPPS电力系统和仿真市场营销副总裁，

Michael Chatlani 说：“项目升级对于 L-3 MAPPS 来说至关重要，因为这能

使我们的最新仿真产品在短期内上市，并再次为大亚湾核电公司提供成功的

解决方案。”

L-3 MAPPS 将会把电力研究院（EPRI）的模块化事故分析程序（MAAP5）

联接到岭澳核电二期工程的仿真机上。MAAP5 是一个执行核电站严重事故分

析的软件程序，涵括堆芯损伤评估和辐射运输评估。仿真机也将配备新型二

维和三维动态、交互的反应堆容器、安全壳厂房和乏燃料池的可视图，将能

够为运营商真实再现在重大核事故中核电站的营运情境 , 其二维图形将启用

L-3’s Orchid® 控制系统，而其 3-D 视觉效果将采用来自 TriLink 系统的

Bridgeworks©。

升级版岭澳二期仿真机除被广泛应用在正常操作、异常、反常紧急事件

的培训中以外，还将被用于与堆芯退化情况相关的训练中。堆芯退化可能导

致燃料熔化，包括包覆氧化事故、氢气产生事故、容器和安全壳故障以及裂

变产物释放。

岭澳二期核电站归属于岭东核电公司所有，由已投入商业运行的两个

CPR1000 核电机组构成：第一个机组于 2010 年 9 月开始运行，第二个机组于

2011 年 8 月投入运行。CPR1000 采用中国的设计标准，是 1080 兆瓦三回路

压水堆。由 L-3 MAPPS 公司联合阿海珐与西门子研制的岭澳二期全范围仿真

机于 2009 年 8 月投入运行。

　　中核集团与阿根廷核电集团高层协调会　　来源：中核网核电站

新闻

AP1000 核电主管道模型图来源：国核工程有限公司

依托项目三门核电站 1 号机组主管道焊接完成

2013 年 4 月 7 日 13 时 58 分，世界首台 AP1000 核电机组——我国三

代核电自主化依托项目三门核电站 1 号机组完成了主冷却剂管道（以下简称

主管道）所有焊口 100% 厚度的实体焊接，主管道 A、B 环路 6 根管段将反应

堆压力容器、蒸汽发生器和反应堆冷却剂泵连接形成一个封闭的环路。

三门核电 1号机组于 2012 年 10 月 4 日正式开始主管道施工，整个

施工过程历时 181 天。主管道焊接采用了激光跟踪测量及 3D 建模拟合、现

场数控坡口精确加工、窄间隙自动焊、激光跟踪测量焊接收缩变形等先进技

术，保障了焊接质量和效率。

新闻85


福清核电 1-6 号机组 500kV 超高压开关站耐压试验全部完成

2013年 4月 3日，福清核电1-6号机组500kV开关站GIS交流耐压试验、

电压互感器 / 避雷器全电压考核试验以及 PT 关口计量绕组角比差试验全部

完成；向四月中旬 500kV 倒送电节点的完成又迈进了坚实的一大步。

GIS属于全封闭气体绝缘设备，交流耐压试验主要为了检验其绝缘性能。

因设备在运输、安装和调试过程中可能导致的绝缘缺陷，以至于引起运行中

其内部产生不同程度的局部放电。长期放电将造成绝缘劣化，甚至击穿和闪

络；所以及早发现其内部的局放现象并防患于未然，对提高 GIS 运行的可靠

性具有很重要的意义。

福清核电超高压开关站 GIS 为 1-6 号机组全厂公用系统，采用 3/2 接

线方式，六串一次性建成。开关站规模大、工期紧、要求高，在国内核电工

程建设中尚属首例（全站能满足六台百万千瓦级机组满功率发电量向电网输

送、一次建成投运但同时又要满足 1# 机组工艺系统调试用电需求）。规模

庞大导致设备电容值也随之增大；且按照《国家电网公司十八项电网重大

反事故措施》的要求，现场的耐压等级需按照出厂耐压标准的 90%（之前是

80%），即相电压达到 666kV；同时由于福建省电网的要求相对更加严格，所

有断路器需做断口耐压。综合以上因素 , 福清联合调试队与多方人员沟通后

决定此次耐压试验分区域分相进行，共计需加压 30 次；之后的 PT/MOA 全电

压考核和 PT 角比差测试则需加压 36 次。这就意味着 57 台断路器、150 把隔

离开关、351 个 SF6 气室，需要重复确认其状态及压力是否满足每一次的试

验要求。本次试验从 2013 年 3 月 13 日开始，期间加班加点，克服福清现场

近期多雨潮湿天气而导致的工期延误；至4月3日中午12点，试验全部完成，

试验结果理想 .

来源：http://www.cnpe.cc

宁德核电 3 号机组首台重型设备吊装就位

4 月 9 日，宁德核电 3 号机组首台主回路重型设备——稳压器顺利吊装

就位，标志着 3 号机组核岛安装工程关键里程碑 ABN3EM2-007 顺利完成，这

为 3号机组主回路重型设备安装创造了良好开端。

宁德核电 3 号机组稳压器高约 13 米、直径约 2.5 米、总重约 85 吨，于

4月 3日卸船运至 3号核岛 20 米平台。9日 13 时 30 分，设备开始起钩翻转，

历经 2个多小时，最终成功吊装就位。

来源：http://www.cni23.com

阳江核电站１号机组冷试完成拟今年建成发电

3 月 31 日凌晨 1:00，中广核集团阳江核电站 1 号机组一回路压力降至

大气压，稳压器排气阀开启，标志着广东阳江核电站 1号机组冷试顺利完成。

自 3 月 25 日冷试开始，阳江核电项目的工程、生产两条线及各参试单

位以细心的准备、默契的配合以及精准的操作，确保了整个冷试升压过程平

稳顺利，一回路含气量、泄漏率等关键指标测算结果良好。经过各单位联合

检查以及华南核与辐射安全监督站现场确认，各项试验结果满足要求，阳江

核电站 1号机组主回路水压试验取得成功。

阳江核电站位于广东省阳江市东平镇沙环，规划建设六台百万千瓦级压

水堆核电机组，是中广核集团在广东地区的第二核电基地。目前 1、2、3、4

号机组已经开工建设，其中 1号机组计划于 2013 年建成投入商业运行。


ACME 试验系统全面进入冷态调试阶段

2013 年 3 月 31 日，我国大型先进压水堆核电站重大专项 CAP1400 非能

动堆芯冷却系统试验设施（以下简称“ACME”）台架完成了历时一天半的主

回路水压试验。

ACME 试验台架为 CAP1400 的 1/3 高度比例试验模型，用于验证 CAP1400

非能动堆芯冷却系统性能及相关热工水力安全分析程序，它完整模拟了原型

电站的主回路和非能动系统。主回路系统通过水压试验标志着台架建安工作

结束，系统将全面进入冷态调试阶段。

国家核电技术研发中心、山东电力工程咨询院有限公司和监理公司共同

见证了此次试验活动。

来源：http://www.snptc.com.cn

福建首台宁德核电１号机组正式投入商业运行

中广核集团今天宣布，宁德核电站一期 1 号机组已于 4 月 15 日完成

168 小时试运行试验，经福建省电力公司确认合格，正式投入商业运行。这

也是我国核电重启后首套机组投产运行，福建省首台核电机发出清洁的电源

开始源源不断地输往福建电网。据测算，该机组日发电量约 2400 万度，可

同时满足项目周边地区 240 万个家庭用电需求，随着该机组并网发电，福建

省清洁能源比例将从目前的 42.56％提高到 45.32％。一期工程四台机组全

部建成后，上网电量相当于福建省 2012 年全社会用电量的 18%，大幅提高清

洁能源在福建能源供给中的比例。

宁德核电站一期采用自主品牌百万千瓦级压水堆核电技术 CPR1000 建

设，拥有 4 台单机容量为 108.9 万千瓦的核电机组。今天正式商运的 1 号机

组于 2008年 2月 18日浇筑第一罐混凝土，2012年 12月 28日首次并网成功，

经过并网之后各功率平台试验和整治性小修，机组的各项性能指标达到设计

标准。

新闻 86


8. 田湾 3 号机组常规岛正式开工

4 月 21 日上午 9 时零 9 分，田湾核电二期工程 3 号常规岛开工仪式在

田湾现场举行，项目业主中核集团江苏核电有限公司，总承包商中国核电工

程有限公司，承建单位江苏电建三公司及四达贝克斯监理公司等单位参加了

开工仪式。田湾核电二期工程是继日本福岛核事故后，我国第一个开工的由

我公司总承包的核电项目，本次 3 号常规岛开工是田湾 3 号核岛正式开工后

的又一重大节点，标志着田湾核电二期工程已全面开工，进入全面施工阶段。


陆丰核电项目环评公示投资３74 亿 2018 年运行

记者 23 日获悉，广东陆丰核电一期工程（选址阶段）环境影响评价目

前正在环保部网站进行受理后公示。公示时间为 2013 年 4 月 22 日—2013 年

5 月 1 日（10 天）。

据悉，陆丰核电厂在 2007 年 10 月被列为国家核电中长期发展规划

“十二五”期间可选择开工候选厂址。该厂位于广东省汕尾市陆丰市碣石镇

以南约 8km 的田尾山，厂址为滨海厂址。陆丰核电厂厂址在行政区划上隶属

于广东省汕尾市辖陆丰市，陆丰市区位于厂址西南方位约 26km，汕尾市区位

于厂址西方位约 45km 处。

环评报告透露，陆丰核电厂规划建设 6 台百万千瓦级压水堆核电机组，

一期工程建设 2 台 AP1000 机组。总投资额约为 374 亿元人民币，资本金占

总投资比例为 25%，其中环保投资约为 7.9 亿元。

陆丰核电厂一号机组计划于2013年12月具备浇注第一罐混凝土的条件，

单机建设周期为 54 个月，两台机组建设相隔 10 个月，一期工程两台机组计

划分别于 2018 年 6 月和 2019 年 4 月投入商业运行。

来源：http://np.chinapower.com.cn/

宁德核电站一期工程由中广核集团、中国大唐集团、福建能源集团共同

出资设立的宁德核电有限公司投资、建设和运营，由中广核工程公司总承包

建设和管理，工程设计、设备制造、工程施工与技术服务等均由国内企业为

主承担。其中，1、2 号机组设备综合国产化率将超过 75％，3、4 号机组设

备综合国产化率将达到 85％。

日本福岛核事故后，根据国家民用核设施安全大检查的结论，宁德核电

站一期在国内在建核电项目中率先完成了安全改进实施工作，进一步提高了

机组应对极端灾害叠加的能力和安全水平。

据测算，宁德核电站一期全部建成后，预计年发电量约 300 亿度，与同

等规模的煤电站相比，相当于减少标煤消耗约 980 万吨，减少二氧化碳排放

约 2400 万吨，减少二氧化硫排放约 23万吨，减少氮氧化物排放约 15万吨。

如果这些煤炭用火车运输，按照 1 节火车皮装载 50 吨，一辆火车共 50 节车

皮计算，一年 365 天不间断运输，每天要有 11 辆火车运煤才能保证供电。

宁德核电站一期的建设对于缓解东南沿海地区电力和能源运输的压力，

优化能源结构和电网结构，实现减少碳排放目标，促进海峡西岸经济区建设

和区域经济、社会和环境可持续发展，建设青山绿水的“美丽福建”将发挥

重要作用。

目前中广核集团拥有在运核电装机 720 万千瓦，在建核电机组 15 台、

总装机 1775 万千瓦，核电安全运行业绩世界领先，2012 年整体业绩进入全

球行业前十。


方家山核电 1 号机组实现压力容器进水冲洗节点

4 月 12 日上午 9 点，随着 1 号机组压力容器内一股股水流喷涌而出，

方家山工程 1 号机组压力容器进水冲洗节点顺利实现。这标志着核岛厂房辅

助系统安装工作基本完成，一回路核辅系统的调试工作将逐步展开。

压力容器进水是对反应堆冷却剂系统、反应堆安全注入系统、化学和容

积控制系统、余热排出系统等几大工艺系统进行的联合冲洗，整个过程由换

料水箱取水，分别对相关系统实施冲洗最终排入压力容器。它也是主回路相

关系统联合试压的先决条件。

为确保该节点安全、顺利实现，秦山核电和各施工单位统筹考虑了 1 号

机组压力容器进水的边界，及时发布了主回路冲洗专项进度计划和进水主线

计划。

87 新闻摘要

日本

一支来自国际原子能机构的团队对日本福岛第一核电站进行了为期一周

的检查，称日本在处理该核电厂损坏机组方面制定的计划具有“逻辑性

和合理性”，但是该厂退役需要的时间将比东京电力有限公司预期的 40

年时间还要长。东京电力有限公司是第一核电厂的运营商。国际原子能

机构核燃料循环和废物部技术总监 --Juan Carlos Lentijo 称“该厂的

退役工作非常繁杂，很难预估出退役项目完成的时间”。Juan Carlos

Lentijo 是此次赴日本福岛检查团队的负责人。他认为从近期来看水质管

理是一个亟待解决的问题，但是要转移地下储存库泄露的污染水则需要

几十年的时间。他认为为保障核电站的安全运行，东京电力有限公司必

须制定一套“更为持久的体系”。4 月 22 日，国际原子能检查小组结束

了检查工作，而就在同一天，东京电力有限公司发布声明称由于老鼠钻

进了变压器造成核电站断电。就在上个月，该公司也发表过类似的声明，

称一只老鼠造成了冷却系统短路。国际原子能机构将于一个月之内发布

官方报告。

阿拉伯联合酋长国

阿联酋核能公司 (Enec) 现在计划建立名为 Nawah 的核能发电联合企业，

该企业将为在建核电站 Barakah 的四个机组奠定基础，该核电站的建造

厂址毗邻沙特阿拉伯。NIW 称反应堆制造商韩国电力公司 (Kepco) 拥有

Nawah 公司 18% 的股份。沙特阿拉伯监管局 (RSB) 负责人 Nick Carter 在

阿拉伯举办的一次会议上宣布 RSB 正在审核 Enec 并网发电所需的许可执

照。Carter 称对于政府支持企业 Enec 来讲，批复手续可能仅仅是走个

过场而已，这将使得 RSB 在核电站建造过程中尽早实现并网发电方面发

挥重要作用。以 Kepco 为首的企业联盟负责核电站建设，Nawah 公司和

Enec 公司负责建立培训体系和教学制度。阿联酋 80%-90% 的人口是外国

人，培训和教学体系的建立旨在帮助这个人口构成多元化的国家实现核

电站运营。一位借调到 Nawah 公司员工称：“我们告诉 Nawah 和 Enec 的

员工，每个人的工作都会或多或少产生一些变动”。

美国

一个由两个党派组成的上议员小组上周提出了一项关于核废料的法案并

提议建立一个专门负责核废料的管理部门，小组称涉及核废料的讨论将

会获得两个党派的支持从而得以顺利进行。该法案与去年的法案的不同

之处在于更加重视加快废料存放风险区以及退役核电站的核废料处理进

程。该项法案的主要支持议员有来自加利福尼亚的 Dianne Feinstein，

田纳西州的 Lamar Alexander，俄勒冈州的 RonWyden 及阿拉斯加的 Lisa

Murkowski。Murkowski 议员说：“我希望我们商讨的草案能够帮助我们

快速解决核燃料循环后期可能产生的诸多重大问题，包括选在临时储存

时是否应该考虑到永久储存的选址等”。接下来该小组会与上议院能源

与自然资源委员会召开商讨会。

印度

纽约时报旗下的印度独立新闻服务机构（简称 IANS）发布了一则报道，

称印度马拉德斯原子能发电站（Maps）因为发电站变压器失火造成 2 号

机组（220MW）停运。Maps 核电站负责人 T.J. Kotteeswaran 接受了

IANS 的电话采访，采访中他讲到：“我们正在检查造成变压器失火的原

因。如果是外部原因，该机组很快就能恢复运行，但如果是内部原因，

则需要时间进行详细排查。”Maps 核电站距离金奈市 70 公里。他还提到

原子能管理局对该事故非常重视。这个机组在前不久刚刚完成为期 40 天

的维修，上周日才开始运行。4 月 15 日事故发生时该机组的运行功率仅

为 110MW，而 1 号机组的运行功率通常为 170MW。由于能源缺乏，印度核

能源公司平时都以较低的功率运行这两个机组。

日本

据相关媒体报道，由于福岛事故造成了日本核电站断网，日本政府一直

要求减少能源消耗。而近两年来日本政府第一次没有发出关于夏季减少

能源消耗的布告。一则政府报告称日本 9 家地方公用事业单位（冲绳电

力公司除外）今年 8月份平均供电盈余 6.3%，而政府称只需要 3% 的盈余

就可以保障日本电力的稳定供应。过去的两年，METI（日本经济贸易产

业省）一直要求按区域缩减电力供应，去年 METI 要求关西电力有限公司

的用户减少 15% 的用电量，今年夏季关西电量供应将盈余 3%。2012 年 7

月日本关西核电站重新启动，而 9 月份该核电站要进行常规燃料和设备

检修。东京电力公司预计 8 月份生产盈余电量总量为 6.7%，该公司为日

本大多数工业区供应电力。

加拿大

加拿大资源与自然资源部部长 Joe Oliver 于本月访问了萨斯喀彻温省，

并与本省省长Brad Wall宣布了加印两国签署加拿大铀出口协议的消息，

只需两国政府批复该协议即可生效。此消息一经发布便引起了公众的注

意，该协议将会对加拿大铀矿产生一定的积极作用。但是加拿大联邦政

府无意提高加拿大铀矿外资公司 49% 股份的上限（尽管加拿大政府此前

曾做出过类此承诺）。近月来萨斯喀彻温省政府在推行政策改变方面做

出了积极的努力，他们认为增加外资公司的股份将会促进阿萨巴斯卡盆

地铀资源产量的增加。萨斯喀彻温省能源局部长称，去年本省铀矿开采

项目投资总额达 1.12 美元。

土耳其

土耳其国家能源局局长在迪拜举办的一次会议上提到土耳其目前的电力

价格是国有电力公司 Tetas 价格的 2/3，阿库尤核电站 4 个反应堆运行

后，该公司需要向俄罗斯支付一定费用。阿库尤核电站前两个反应堆

生产的电量将达到整个核电站的 70%，根据 2010 年俄罗斯和土耳其签

订的一项协议，Tetas 将连续 15 年按照 12.35 美分 / 千瓦时的价格购

买电力，其中 70% 的电力是由 1 号机组的两个反应堆生产的，30% 是由

2 号机组的两个反应堆生产的。由于水利发电产能较高，核能发电目前

价格在 8 美分 / 千瓦时。Selvitop 称阿库尤核电站预计于十年内正式

运行，能源局认为届时能源价格将会超过与俄罗斯国有企业原子能公司

分公司 Rosenergatom 签订的合同价格。上周土耳其能源经济学会会长

GurkanKumbaroglu 在华盛顿举行的一次会议上辩称按照名义条款来看合

同价格要比实际价格低，他讲到：“2019 年阿库尤核电站第一个反应堆

运行后，每千瓦时的价格将会减少至 6到 7美分”。

88核电词汇

asbestos paperaseismicaseismic bearing padaseismic plateaskarel-filled transformeraspect ratioasperity junctionsasphaltasphalt roofingasphalt-based solidifcationassemblyassemblyassembly drawingassembly fixture (control rods)assessmentassigneeassignment assignment check assignment drawingassistant shift supervisor assumed assumption asymmetricasynchronous motoratmospheric pressureatmospheric relief valveatmospheric steam dumpatmospheric steam dump valveatomic chargeatomic energyatomic mass unitatomic numberatomic ratioatomic weightatomize v.attachingattachmentattachment modeattachment pointattack (corrosion)attenuationattenuation coefficientattentuation factorattributeaudible alarmaudible signalsaudible warning deviceaudio radiation indicatorauditaudit follow-upaudit planaudit record

是棉纸抗震的抗震基础（抗震垫）抗震支承板充 askarel 的变压器纵横比、高宽比粗糙接合沥青沥青屋面沥青固化装配组件装配图组装架（控制棒）评价受托者、代理人用途用途核查功用图助理直长假定的假定不对称的异步马达大气压大气释放阀、安全阀蒸汽向大气排放蒸汽向大气排放阀原子的电荷原子能原子质量单位原子序数原子比例原子量喷射、雾化附着附件固定模式固定点腐蚀衰减衰减系数减弱因子特性、标志音响报警音响信号音响报警器音响辐射监测器监查追踪监查监查计划监查记录

核电专业词汇Nuclear GlossaryEnglish Chinese English Chinese

audit reportauditoraustenitic steelaustenitizingauthorityauthorizationauthorization decree (plant)authorization to proceedauthorization to proceed with fabricationauthorizationauthorized for testingauto-manual control stationautoclaveautogenous weldingautomatedautomatic chemical monitoring and control deviceautomatic controlautomatic control assemblyautomatic control relayautomatic control systemautomatic controllerautomatic level (surveying)automatic remote-controlled plugging automatic remote-controlled plugging systemautomatic roll-type filterautomatic rotating-type filterautomatic sample changerautomatic spiral ratchet screwdriverautomatic surface examinationautomatic switchautomatic synchronization unitautomatic welding automatic welding machineautonomousautotransformerauxiliary actuating deviceauxiliary alternatorauxiliary boilerauxiliary bridge (fuel handling)auxiliary buildingauxiliary building sump pumpauxiliary contactorauxiliary exciterauxiliary feedwaterauxiliary feedwater pump (motor and turbine-driven)auxiliary feedwater storage tankauxiliary feedwater supply (steam generators)auxiliary generator

检查报告监查员奥氏体钢奥氏体化管理局审定、批准批准建设（电厂）批准开工批准开工制造审定批准实验自动 - 手动控制站高压釜自动气焊自动化的自动化学监控装置

自动控制自动控制组件自动控制继电器自动控制系统自动控制器自动化水平仪自动遥控堵塞自动遥控堵塞系统

自动旋滚式过滤器自动旋滚式过滤器自动样品更换器自动螺旋齿杆起子自动表面检查自动开关自整步装置自动焊接自动焊接机自备的自耦变压器辅助自动装置辅助交流发电机辅助锅炉辅助桥吊辅助厂房辅助厂房地坑泵辅助接触器辅助励磁机辅助给水、事故给水辅助给水泵

辅助给水箱

辅助给水辅助交流发电机

L-3逼真的仿真技术以效率共创未来

L-3 MAPPS L-3com.com

L-3的超级仿真培训系统采用Orchid 仿真技术，为电厂操作人员提供真实的操作环境，帮助他们获得处理任何紧急事故的经验。不管是多复杂，多危险的事故工况，都可以在仿真器上实时逼真地推演，对事故工况提供有效的监视并能对事故工况进行适当的调整。

请点击www.L-3com.com/MAPPS您可以详细地了解我们近40年所积累的核电仿真领域的相关经验，以及我们能如何改变您的现在和未来。

COSPP_New Build Efficiency_July 2012.indd 1 9/12/2012 2:39:03 PM

89 新闻摘要

L-3逼真的仿真技术以效率共创未来

L-3 MAPPS L-3com.com

L-3的超级仿真培训系统采用Orchid 仿真技术，为电厂操作人员提供真实的操作环境，帮助他们获得处理任何紧急事故的经验。不管是多复杂，多危险的事故工况，都可以在仿真器上实时逼真地推演，对事故工况提供有效的监视并能对事故工况进行适当的调整。

请点击www.L-3com.com/MAPPS您可以详细地了解我们近40年所积累的核电仿真领域的相关经验，以及我们能如何改变您的现在和未来。

COSPP_New Build Efficiency_July 2012.indd 1 9/12/2012 2:39:03 PM

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