CANDU® - SNC-Lavalin · requirements of ASME Code Section III (Nuclear Code). Some unique CANDU equipment (Calandria, pressure tubes, Calandria tubes) are designed and manufactured

›- Copyright -

›CANDU® ›Opportunities and Challenges for CANDU Nuclear Supply Chain in Poland . Potential for High Level of Localization and Energy Independence 2017 January 30 Jerzy Parkitny, P.Eng Manager, Equipment and Products

›- Copyright - ›CANDU ® Opportunities and Challenges for CANDU Nuclear Supply Chain in Poland . Potential for High Level of Localization and Energy Independence 2017 January 30 Jerzy Parkitny, P.Eng. Manager, Equipment and Products

A world leader Founded in 1911, SNC-Lavalin is one of the leading engineering and construction groups in the world and a major player in the ownership of infrastructure. From offices in over 50 countries, SNC-Lavalin’s employees provide EPC and EPCM services to clients in a variety of industry sectors, including mining and metallurgy, oil and gas, environment and water, infrastructure and clean power. SNC-Lavalin can also combine these services with its financing and operations and maintenance capabilities to provide complete end-to-end project solutions.

- Copyright - © [2016] SNC-Lavalin Group and its member companies. All rights reserved. Unauthorized use or reproduction is prohibited. 3

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AGENDA

5

1. Background and a short history of CANDU® technology 2. CANDU vs. PWR 3. Nuclear Equipment Localization & Technology Transfer

Experience 4. Potential for Localization of NSP (Nuclear) Process

Equipment in Poland 5. Supplier Qualification 6. CANDU - The Right Choice for Poland

- Copyright - © [2016] SNC-Lavalin Group and its member companies. All rights reserved. Unauthorized use or reproduction is prohibited.

Background and short history of CANDU technology

Background and history of CANDU technology

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What is CANDU? = CANada-Deuterium-Uranium Power System • Sounds like “Can Do” - and so: “Canadian people Can Do this job”. • Developed from 1945 to 1995, using Canadian resources + international

cooperation • Uses natural uranium fuel. Enriched fuel was not available in Canada at the start

and Canada’s role during the war was to work on NU reactors. • Uses heavy water as reactor coolant and moderator • CANDU is a channel-type reactor - best for NU and heavy water • This project was started before the end of the Second World War. At that time

Canada was a developing country. • In about 1955, the Province of Ontario used all of its hydraulic generation. They

had no oil, no coal, no gas -- and so, No Choice but Nuclear! • Many British, French, and other scientists moved to Canada to escape the war –

they started the Canadian nuclear power program. Note: Lew Kowarski supervised the construction of Canada's first nuclear reactor (ZEEP) at the Chalk River Laboratories in 1945.


Official Use Only 8

• The most basic decision was to use natural uranium fuel

• After this, it was decided to use heavy water as the moderator -- Better than Graphite!

• Heavy water absorbs neutrons much less probably than regular water, so it’s

significantly easier to sustain a neutron chain reaction with heavy water. This allows CANDU reactors to operate with natural uranium (no enrichment necessary).

• Atomic Energy of Canada (AECL) wanted to use a pressure vessel for the first demonstration. This idea was stopped by the electric utilities - They Wanted Big Reactors!

• A pressure vessel of this type using heavy water would be too big for manufacture in Canada. (the German design in Argentina gives the proof.)

• The designers changed CANDU to a channel-type design.

Background and history on CANDU technology



CANDU® Highlights

› Mid size reactor for mid size economies 700 MWe design

› HIGH Localization potential Relative simplicity of nuclear equipment (High Value Added)

› Fuel cycle flexibility Potential for recycled U and Thorium / Very simple fuel bundle design (can use different nuclear fuels). Fuelling on-line at full power

› Superior performance Average lifetime CF: 88% worldwide / Can undergo an outage at convenient time

› Energy independence No need for uranium enrichment

› Enhanced safety Inherent features to address Fukushima concerns

› Is capable of load following as proven in several CANDU 6 plants

› Contains all reactor control, shutdown systems and nuclear measuring devices in cool, low pressure moderator (no-pressure driven control rod ejection possible)


Range of possible CANDU fuel cycles

The CANDU design uses natural uranium fuel. An important consideration in selecting a nuclear power plant system is that it can accept a variety of fuel types. CANDU reactors have the capability to use the following fuels:

› used fuel from light-water

reactors, › Natural uranium , › slightly enriched uranium (SEU), › recovered uranium (RU), › mixed oxides (MOX), › and thorium.

http://en.wikipedia.org/wiki/File:CANDU_fuel_cycles.jpg


CANDU 6: Lifetime Capacity Factor

0.0%10.0%20.0%30.0%40.0%50.0%60.0%70.0%

80.0%

90.0%

100.0%

72.7% 77.9%

80.0%

93.9% 95.0% 96.1%

84.80% 89.60% 93.60% 90.60% 90.50%


CANDU 6: Delivery Performance Wykonanie Dostaw

In-Service Plant Status 1996 Cernavoda Unit 1, Romania On budget, on schedule

1997 Wolsong Unit 2, South Korea On budget, on schedule



2002 Qinshan Phase III Unit 1, China

Under budget, 6 weeks ahead of schedule

2003 Qinshan Phase III Unit 2, China

Under budget, 4 months ahead of schedule

2007 Cernavoda Unit 2, Romania On budget, on schedule

CANDU vs. PWR


CANDU vs. PWR


CANDU® CODES and STANDARDS

CANDU

PWR (USA) PWR ( AREVA)

All Nuclear Class equipment is designed and manufactured to the requirements of ASME Code Section III (Nuclear Code). Some unique CANDU equipment (Calandria, pressure tubes, Calandria tubes) are designed and manufactured to CSA N285.0 Class 1(with references to ASME Sec III, Class 1)

All Nuclear Class equipment is designed and manufactured to the requirements of ASME Code Section III ( Nuclear Code)

All Nuclear Class equipment is designed and manufactured to the requirements of RCC-M French Nuclear Code

Refer to STP-NU-051-1 “CODE COMPARISON REPORT For Class 1 Nuclear Power Plant Components” http://files.asme.org/STLLC/33774.pdf

Discuss: Application of the ASME Nuclear Code on recent CANDU projects in Romania and Argentina

http://files.asme.org/STLLC/33774.pdf


CANDU vs. PWR

CANDU: Lowest Uranium Consumption

0

5

10

15

20

25

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CANDU saves 30% uranium to deliver each TWh compared with a typical PWR

Saving ~30.0 %

CANDU Typical

(Q3)

PWR Typical

Mg N

U / T

Wh

3.25%~ 4.5% 0.71% U-235 Enrichment


CANDU vs. PWR

18 - Copyright - © [2016] SNC-Lavalin Group and its member companies. All rights reserved. Unauthorized use or reproduction is prohibited.


The Fuel Cycle Advantages & Differentiators of CANDU

Reactor physics › D2O moderator/HTS › Softer (thermalized) spectra › Minimized parasitic absorption › High neutron economy

On-power fuelling › Low excess reactivity › Highest uranium utilization

Simple and small fuel bundle › Enabling on-power fuelling › Flexible design › Easier transition between fuel types

Versatile pressure tube design › Capability to have different fuel mixes

Minimal (in some cases no) changes in reactor design to use different fuels

CANDU ® NUCLEAR EQUIPMENT LOCALIZATION & TECHNOLOGY TRANSFER EXPERIENCE


NUCLEAR EQUIPMENT LOCAL SUPPLY UNIQUE CANDU® OPPORTUNITY

SCOPE

PWR CANDU

Project management of new plant construction (which can account for up to 15% of overall project value)

Supply of raw materials (e.g., steel, cement, etc.); On-site erection / installation (‘mechanicals’): Supply chain management; Specialist equipment supply (instrumentation & control, and electrical);

Limited

Limited

Electrical, on-site installation; Supply of large forgings for Nuclear Steam Supply Systems (NSSS); NO NOT REQUIRED

(forging size much smaller)

Supply of other forgings and castings for the nuclear island: NO HIGH Specialist component supply (valves, pumps, cables, etc.); NO LIMITED Manufacture of nuclear island equipment, including steam generators, pressurizers, major HXs and Pressure vessels, primary circuit pipework, and its engineering support (with qualification and investment);

NO HIGH

Manufacture of reactor pressure vessel (RPV) / Calandria (with qualification and investment);

NO HIGH

BOP Large Equipment / HX , Pumps. Turbine , Generator NO HIGH


NUCLEAR EQUIPMENT LOCALIZATION & TECHNOLOGY TRANSFER

Factors that allow CANDU technology transfer and localization of NSP (nuclear) equipment in a host country:

› Pressure retaining nuclear class equipment (high value added) : physical size and weight within industrial capability of developed economies (example: S. Korea, Romania, Argentina)

› The complete fuel cycle, from uranium mining (in some countries) through to fuel fabrication and interim or final disposal of spent fuel in host country.

› Simple nuclear fuel manufacturing.

**These key factors are critical in allowing a host country to achieve

“nuclear energy” self sufficiency**

› Heavy water production can be localized, if desired. (D2O is required for the first fill-up and make-up.)


NUCLEAR EQUIPMENT LOCALIZATION CANDU Localization (% local content) - Republic of KOREA

The Korean Experience: 1983-1997

~25%

Wolsong Unit 1

~58%

Wolsong Unit 2

Wolsong Unit 3

~63%

~75%

Wolsong Unit 4

CANDU 6 – CANDU Critical Nuclear Equipment A Short History of Technology Transfer - S. Korea

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›The successful performance of the Wolsong 1 CANDU plant led to the purchase of a second unit (Wolsong 2) in 1990. This unit entered commercial operation in 1997 July.

›The level of localization achieved on Wolsong 2 was 58%, rising to 62% on Wolsong 3 and 75% on Wolsong 4.

›The average localization rate for Wolsong 2, 3 and 4 was therefore 65%.

›Equipment localization for Wolsong 3 and 4 was 50% for the Nuclear Steam Supply Systems (NSSS), 80% for Balance of Plant (BOP) systems and 90% for the Turbine Generators.

›This level of localization is anticipated to be achievable

›in Poland for a project of four CANDU units.

›



NUCLEAR EQUIPMENT LOCALIZATION CANDU Localization (% local content)– ROMANIA

The Romanian Experience: 1983-2007

New project C 3&4

~40% (by weight)

Cernavoda Unit 1

~60% (by weight)

Cernavoda Unit 2

Cernavoda Unit 3 NEW PROJECT

TBD

TBD

Cernavoda Unit 4 NEW PROJECT


CANDU EQUIPMENT (NUCLEAR) Manufactured in ROMANIA

EQUIPMENT REMARKS Pressurizer, ASME Sec III, Class 1 Manufactured for Cernavoda 2

Degasser Condenser, ASME Sec III, Class 1

Manufactured for Cernavoda 2

Major Heat Exchangers – Shutdown Cooler, Moderator HX etc, ASME Sect III Class 1 and 3

Manufactured for Cernavoda 2

Reactivity Mechanism Deck

Manufactured / assembled for Cernavoda 1 & 2

Feeder and Feeder Header Frame

Manufactured / assembled for Cernavoda 2

Fuel Handling Equipment

Manufactured / assembled for Cernavoda 2

CANDU Fuelling Machine Tested for Cernavoda 2 Equipment and Personnel Air Locks Manufactured / assembled

for Cernavoda 1 &2 Calandria (CANDU Reactor) Manufacturing technology acquired.

Partially manufactured for Cernavoda 3.

Steam Generators Manufacturing technology acquired. Equipment planned to be manufactured for Cernavoda 3.


NUCLEAR EQUIPMENT LOCALIZATION CANDU Localization (% local content) – ARGENTINA

The Argentinean Experience - 2010 - present

EMBALSE Refurbishment ***

CONUAR, FAE –manufacturing of

critical elements of the reactor,

IMPSA – steam generators under license from B&W

Canada ***

ATUCHA NEW PROJECT

CANDU ® Potential for Localization of NSP (Nuclear) Process Equipment in Poland

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CANDU Nuclear Class Equipment Potential for Localization

CANDU Main Process Equipment: • Calandria / Feeders / Primary

Headers • 2 loops, carbon steel • 4 primary coolant pumps, • 4 steam generators • Pressurizer • Degasser Condenser • Major Heat Exchangers • Nuclear Tanks And Vessels

*Red font indicates high localization potential in Poland


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CANDU SYSTEM – BASIC MATERIAL REQUIREMENTS

› CANDU Primary Heat Transport System chemistry permits the use of carbon steel

› Carbon Steel used for primary circuit (NSP) piping and most of the pressure boundary nuclear equipment, with only limited used of stainless steel.

› Alloy 800 is used for nuclear tubes (steam generator, heat exchangers) as opposed to the Alloy 600 or 625 used in PWRs.

› NOTE: Argentina localized manufacturing of I-800 tubes.

› Stainless steel is used for some internal parts, subject to flow-assisted corrosion / erosion.


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NUCLEAR EQUIPMENT LOCALIZATION CALANDRIA (REACTOR)

›The Calandria is manufactured by heavy industry & shipyards

› (Potential manufacturer: Shipyards)


Potential for Localization in Poland - Calandria

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• The most critical and a high value-added component of a CANDU reactors is the Calandria (reactor).

• Calandria is designed by Candu Energy Inc. and manufactured by heavy industry and shipyards.

• Potential manufacturer in Poland: Energomontaż Północ Gdynia

• Energomontaż has significant experience in manufacturing steel structures of a similar nature (including reactor building liner for Olkiluoto 3).

• Calandria Assembly • 8.46 m wide

• 8.53 m high

• 7.82 m long

• Approximate shipping weight 282 tones

• Code Class CSA N285.0 Class 1

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• High value-added equipment • Critical part of the Heat

Transport System • Code Class CSA N285.0

Class 1(ASME Sec III, Class 1)

• Designed by Candu Energy • Manufactured by heavy

industry, like Babcock and Wilcox Canada, also in Korea, Romania and Argentina

• Potential manufacturer in Poland: RAFAKO, FAMET

Potential for Localization in Poland – CANDU Feeder Header Frame Assembly

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• High value-added equipment

• Manufactured by heavy industry

• Design by Babcock and Wilcox Canada

• Manufactured in Canada, Korea, Argentina.

• Potential manufacturer in Poland: RAFAKO

• Steam Generator Data o Quantity – 4

o Shipping weight: approx. 220 tones

o Material: Tubes I-800; Shell Carbon Steel

o Heat Transfer Area (per SG): 3195 m2

o Heat Transferred per four (4) SGs ; 2064 MW(the)

o Code Class CSA N285.0 Class 1(ASME Sec III, Class 1)

o Design Pressure (D2O) 11 MPa (g)

o Design temperature (D2O) 318°C

o Design Pressure (H2O) 5 MPa (g)

o Design Temperature (H2O); 265°C

Steam Outlet

Potential for Localization in Poland – Steam Generator

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• High value-added equipment • Designed and manufactured by

vendors to Candu Energy’s requirements

• Code Class CSA N285.0 Class 1(ASME Sec III, Class 1)

• Manufactured by heavy industry, like Babcock and Wilcox Canada, also manufactured in Korea and Romania.

• Potential manufacturers in Poland: RAFAKO, F.W. FAKOP, FAMET

Potential for Localization in Poland – Pressurizer & Degasser Condenser

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›Variety of Nuclear and Non Nuclear Vessels / Tanks ›Code classification: CSA N285.0, Class 1, Class 3 and Class 6 = ASME SECTION III and VIII ›Large Tanks (water storage) materials – carbon steel ›Smaller Tanks (various D2O systems) – austenitic stainless steel ›Variety of Nuclear and Non-Nuclear Vessels ›Tanks are designed and manufactured by vendors to Candu Energy’s requirements ›Manufactured by power industry, including number of vendors in Canada. ›Also manufactured in Korea, Romania, China, Japan ›Potential manufacturer in Poland: RAFAKO, F.W. (FAKOP), FAMET, other suppliers of tanks and vessels.

Potential for Localization in Poland – Nuclear Tanks & Vessels

CANDU ® Supplier Qualification

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Qualification Process Pre-Requisite

All potential Nuclear Suppliers shall posses or be in a process of obtaining: •Authorization of a Nuclear Regulator (Polska Agencja Atomistyki - – National Atomic Energy Agency)

•Authorization by Jurisdiction (Urząd Dozoru Technicznego / Technical Inspection Authority)

•Certification of an organization's quality assurance program in accordance with Section III of the ASME Boiler and Pressure Vessel Code (BPVC) for components installed in nuclear facilities.

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CANDU Supplier Qualification Process

•There are three main aspects that are subject to Candu evaluation.

1.QA Program 2.Design, Manufacturing, Inspection, Testing, Handling &

Shipping Capabilities. 3.Product Qualifications •Prototype Qualification •Pre-production Qualification

•We will concentrate on item 2 = Design, Manufacturing, Inspection, Testing, Capabilities

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Engineering and QA Program Assessment •Engineering and QA Assessment is carried out to the applicable Codes and Standards:

–ISO 9001 –ASME NCA-4000 (applicable N-stamp or Canadian CSA

N285.0 certifications) –ASME NCA-3800 for Material Organizations (QSC or

Canadian CSA N285.0 certification) –Required authorized Inspection agreements with the

Authorized Inspection Agency •How the assessment is carried

– Review of Current certifications – Review of QA Manual and audit – Initial Capability Assessment Survey

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Initial Capability Assessment Areas Assessed •Plant size, layout & location •Staffing levels & Personnel Qualification •Current product lines & specialty •Design capabilities, if design scope by the manufacturer •Manufacturing capabilities (welding, machining, forming, assembly, heat treatment, plating, cleaning, pickling, other processes related to the product)

Process •Team of Candu engineering, QA and commercial specialists •Request and review of initial data (Organization, QA Manuals, Contact inf.)

•Standard Checklists •Plant Survey

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Product Qualifications •Prototype Qualification :

•Purpose and scope of prototype qualification is to confirm acceptability of supplier’s manufacturing, inspection & test processes to satisfy product design and performance criteria.

•How Product Qualifications are Performed – Shop evaluations and tests – Laboratory tests and evaluations

•Prototype qualifications are typically destructive and are performed prior to award of P.O.

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Product Qualifications

•Pre-production Qualification :

•Purpose and scope of pre-production qualification is to confirm that finally established and accepted processes are under control and are capable of consistently producing products that meet specification requirements

•Pre-production qualifications are a combination of destructive and non-destructive testing and are performed after P.O. award

•Product Qualifications are product specific and are not covered in this presentation

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Qualification Process - Success Factors

•Availability and proper implementation of related processes and capabilities / control of all design and manufacturing steps

•Use of qualified / established sub-contractors and material manufacturers (Forging, Ingots, Strips, Parts)

•Availability of time and resources to perform prototype qualification

•Use of qualified Engineering and QA oversight personnel & organizations

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Project Schedule Long Lead Equipment Procurement

Supplier Qualification • Calandria Supplier Qualification: Any selected supplier have to undergo qualification – 1 to 2

years *

• Steam Generator Supplier Qualification Canadian supplier is qualified Local supplier has to be qualified - 1 to 2 years *

• Feeder Header Assemblies Supplier Qualification Canadian supplier is qualified Local supplier has to be qualified - 1 to 2 years *

* PO can be placed as early as three to six months after the start of qualification.

CANDU The Right Choice for Poland

CANDU ADVANTAGE

The use of standard CANDU 37 element Natural Uranium fuel offers the most economical reference fuel cost of any technology; with no enrichment requirement, this offers the greatest opportunity for localization of full fuel supply, should this be of interest.

The very high reliability of CANDU fuel, and the ability to remove any defected fuel immediately from the core, offers an environmental advantage for CANDU that could be reflected in the bidding process.

Candu, as a non-fuel manufacturer, is in a better position than most vendors, to ensure that fuel supply is not used as a profit centre to offset unreasonable plant capital cost estimates.

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CANDU Advantage Criterion - # 1 Energy Independence and Energy Self-sufficiency

›This is defined as the possibility of producing a country’s own nuclear fuel, and the ability to use various nuclear fuels today and in the future.

›There are several systems that, in a decade or two, will be able to fulfill the requirements of criterion # 1. However, there is only one system that has the technological potential to fulfill this criterion now - this system is CANDU (Canadian Deuterium Uranium).

›The possibility of using natural uranium, as well as other fuels, such as thorium, and also spent fuel from other reactor types (e.g., PWR, which dominates the European market for nuclear energy), allows for energy independence from other countries today and in the long term.

›A good example of meeting this criterion is Romania and Argentina .


CANDU Advantage Criterion - # 2 Technology Transfer

Taking into account the experiences of those countries that have nuclear power plants and an industrial base similar to that of Poland, one should consider the physical size of the offered systems. For the key pressure retaining equipment, the practical limits for the local industries are equipment size (dimensions) and weight.

›Only one available and proven nuclear energy system allows for the manufacturing of most of these key items in Poland. This system is the CANDU system.

›Examples of a high degree of localization of CANDU equipment are Romania, South Korea, China and also Argentina.

›Polish industries are well positioned (pending technology transfer and qualification) to manufacture CANDU NSP process equipment.


CANDU Advantage Criterion - # 3 Construction Time and Unit Power Output

›Size of the unit (MWe) shall be suitable for the existing grid. Large units can easily destabilize the entire grid if unexpectedly shut down.

›CANDU, with approx. 740 MWe rated power, is ideally suited for the electric grid in northern Poland.

›Several of the nuclear systems considered by Poland claim that they have been built in about 5 to 6 years ? Based on the already built projects or projects under construction, you can arrive at your own conclusion

›CANDU holds the world record for NPP construction at QINSHAN Phase III ( China) – completed in less than 5 years.

›Cernavoda Unit 2 was built on time and schedule (under Canadian management)


CANDU Advantage Criterion - # 4 Own Fuel - Natural Uranium in Poland

› In Poland, there are uranium deposits in the Sieroszowice-Lubin Basin. The uranium content of the ore oscillates at 60 parts, with a copper content of 2 percent. Total uranium ore deposits are 144 thousand tons. This is equivalent to about 900 gigawatts of electric power.

› About 1700 tonnes of uranium per year are thrown into the waste heap in the Sieroszowice-Lubin Basin. This uranium can be processed for nuclear power application in a CANDU reactor (NO NEED for enrichment). This amount of uranium would be enough to power 10 reactors with a capacity of 1000 MWe each. *

Source: Chajduk, E., Polkowska-Motrenko, H.,“Uranium resources in Poland - the past and present,” Institute of Nuclear Chemistry and Technology, Warsaw, Poland. .

http://www.unece.org/fileadmin/DAM/energy/se/pdfs/UNFC/ws_IAEA_CYTED_UNECE_Oct12_Lisbon/12_Chajduk.pdf

http://www.mg.gov.pl/Bezpieczenstwo+gospodarcze/Energetyka+jadrowa/Najwazniejsze+informacje+o+energetyce+jadrowej/Cykl+paliwowy








Thank You

CANDU® OFFERS

›Nuclear energy self-sufficiency

›High level of localization of critical nuclear equipment

›System size suitable for your electrical grid

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DISCUSSION and Questions

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Documents

CANDU® - SNC-Lavalin · requirements of ASME Code Section III (Nuclear Code). Some unique CANDU equipment (Calandria, pressure tubes, Calandria tubes) are designed and manufactured