51
此处的位置是一级标题/ Here is the title 1 核电厂全寿期的老化与寿命管理及实践 Ageing and Life Management and SNPTC’s Practice Covering Full Life Cycle of NPPs 2016. 11. 02 窦一康 DOUYikang

Safety aspects of the full life cycle AM

Embed Size (px)

Citation preview

Page 1: Safety aspects of the full life cycle AM

此处的位置是一级标题/ Here is the title 1

核电厂全寿期的老化与寿命管理及实践

Ageing and Life Management and SNPTC’s

Practice Covering Full Life Cycle of NPPs

2016. 11. 02

窦一康 DOU, Yikang

Page 2: Safety aspects of the full life cycle AM

目 录 Content

一. 核电厂全寿期老化管理的安全性考虑 I. Safety aspects of NPPs’ full life cycle of AM

二. 核电厂寿命管理的经济性考虑 II. Economic considerations for life management of NPPs

三.SNPTC的实践

III SNPTC’s Practice

Page 3: Safety aspects of the full life cycle AM

3

一. 核电厂全寿期老化管理的安全性考虑

I. Safety aspects of NPPs’ full life cycle of AM

Page 4: Safety aspects of the full life cycle AM

4

1 核电厂全寿期老化管理的安全性考虑 Safety aspects of the full life cycle AM

2009年国际原子能机构出版了“核动力厂老化管理导则(NS-G-2.12) 引入了超前主动老化管理的理念

In 2009 IAEA published a guidelines on “Ageing

Management for Nuclear Power Plants” (NS-G-

2.12), introducing concept of proactive AM.

该导则不仅对核电厂运行运行阶段提出老化管理要求,还要求将老化管理理念拓展到设计、建造、调试和退役各阶段,覆盖核电厂全生命周期

AM is not only required for operational stage,

but also required for full life cycle stages of

NPPs, including design, fabrication,

construction, commissioning and

decommissioning

2012年国家核安全局参照IAEA导则出版了核安全导则“核动力厂老化管理(HAD103/12)”

In 2012, NNSA published safety guideline

Ageing management for NPPs (HAD 103/12)

based on similar IAEA guideline.

Page 5: Safety aspects of the full life cycle AM

Design Constr

uction operating

Operating within design life LTO

Decommis

sioning

PSAR FSAR PSR-1 PSR-2 PSR-n+ LR app.

……. PSR-

n+1

PSR-

n+m +D

app

Nuclear

safety

regulatory

AMP(traditional understanding)

PLEX Plan Decommissioning plan

Reliability starts from design and is maintained throughout the full life cycle of NPP

EQ program; identifying ageing deg.; exp. Feedback; materials; monitoring; facilit. O&M; Ageing issues for FSAR

Data by vendors; exp. Feedback; baseline data; testing sampling; hot spots ident.; vib. monitoring

Resource allocation: Screening; ageing mechanisms; ageing detection; ageing mitigation; ageing assessment; data collection and record keeping; impact of significant modification……

Maintaining availability of SSCs for decommissioning activities through AMP

1 核电厂全寿期老化管理的安全性考虑 Safety aspects of the full life cycle AM

Page 6: Safety aspects of the full life cycle AM

1 核电厂全寿期老化管理的安全性考虑 Safety aspects of the full life cycle AM

阶段Stage

需求

Needs

围绕需求应开展的活动

Activities arouse from needs

相关技术支撑

Related technical support

设计

Design

鉴定计划

EQ programme

1)设计基准Design basis conditions for

normal operation and DBA;

2) EQ要求及文件包 EQ requirements

and document package

对核安全设备开展EQ活动

EQ activities based on design

requirements to demonstrate

qualification of all safety

related equipment

识别并评估潜在的老化机理 Identify and

evaluate potential

ageing mechanisms

作为设计文件形成一系列老化机理分析报告

A series of ageing mechanisms analysis

reports as part of design documents

根据材料、环境、受载情况对老化机理加以分析

Analysis of potential ageing

mechanisms based on material

properties, environment

conditions and loadings

经验反馈

Experience

feedback

经验反馈报告 Comprehensive

experience feedback report based on an

effective coordinative mechanism

需要时开展失效分析

Failure analysis when

necessary

在线监测

Online monitoring

设计时考虑部分在线监测To sensible

ageing mechanisms, online monitoring

should be considered in design

建立各类在线监测系统

Establishment of various

monitoring systems

便于维修

Facilitate of

inspection and

maintenance

建造效率与便于维修之间的平衡

Compromise of construction schedule

and facilitation of O&M

确认可达性与可维修性

Demonstration of accessibility

and capability of maintenance

作为最终安全分析报告的特殊专题

As a special topic

for FASR

向监管当局说明老化管理策略 Explain

AMP policies, EQ requirements,

condition monitoring measures to

safety regulatory during design stage

补充相关的FSAR技术支持材料

A series of additional technical

support documents for FASR

Page 7: Safety aspects of the full life cycle AM

贯穿于核电厂全寿期的EQ EQ Activities throughout whole life of NPPs

设计输入

Design input

Identifying PIEs

Environmental

conditions

Safety functions.

Equip. list

开展EQ

EQ Implementation

EQ Reqirements and

criteria, methodologies

Programmes and

procedures, QA…

Identifying resources

EQ implementation by

test of analysis

Documentation

反馈

Feedback

Design and

Construction stage

Operation stage

Control of maint

Control of change

Environment

monitoring

Degradation and

failure analysis

Experience feedback

维持EQ

Maintaining EQ

Page 8: Safety aspects of the full life cycle AM

R&D needs from

Conceptual

renovation,

Experience feedback

Safety regulatory

requirements, such as

EAF

Design by

analysis to

satisfy the

new needs

Confirm through

analysis,

qualification,

inspection and

monitoring

研发R&D 设计Design 确认Confirm

feedback

研发、设计和确认的关系

Relations of R&D, Design and Confirmation

1 核电厂全寿期老化管理的安全性考虑 Safety aspects of the full life cycle AM

可靠性始于设计并应该贯穿于核电厂生命周期的全过程 Reliability starts from design and is maintained throughout the full life cycle of NPP

Page 9: Safety aspects of the full life cycle AM

可靠性始于设计并应该贯穿于核电厂生命周期的全过程 Reliability starts from design and is maintained throughout the full life cycle of NPP

CAD interface

Preliminary design

Functions, materials, layout, shape,

etc.

Steady loading Design by analysis Transient loading

Temp & Pres. Others Temp.& Pres. Mec. Seis. LOCA Other DBA

Static analysis CFD analysis Dynamic analysis

Transient

database

P-T limit

Seismic

input

EAF

effects

Parameter analysis models

Analysis on stress, deformation, fatigue, fracture and sealing performance, etc.

Material

database Loading combination

Stress

limits Fatigue limits Critical fracture

intensity limits

Deform

limits

Sealing

criteria

Functional

requirement

s

Pass the design by analysis

Completion of preliminary design

CAD interface Feedback to preliminary design

N Y

Mec.

典型的分析法设计流程 Typical flowchart of

design by analysis

Page 10: Safety aspects of the full life cycle AM

1 核电厂全寿期老化管理的安全性考虑 Safety aspects of the full life cycle AM

例:蒸汽发生器分析法设计 Design by analysis for SG

Page 11: Safety aspects of the full life cycle AM

1 核电厂全寿期老化管理的安全性考虑 Safety aspects of the full life cycle AM

例:反应堆压力容器分析法设计 Design by analysis for RPV

Page 12: Safety aspects of the full life cycle AM

1 核电厂全寿期老化管理的安全性考虑 Safety aspects of the full life cycle AM

例:堆内构件流场分析 CFD analysis for RI

Page 13: Safety aspects of the full life cycle AM

1 核电厂全寿期老化管理的安全性考虑 Safety aspects of the full life cycle AM

例:分析法设计的各类应用 Various application of analysis by analysis

核电站管道及其支撑的应力分析、地震分析、疲劳分析 Stress analysis, seismic analysis, fatigue analysis of the NPP piping and supports 管道流体热分层、LBB、水汽锤、回路声振动、管道部件等分析和评定 Analysis and evaluation of piping thermal stratification, LBB, water/steam hammer, acoustic vibration, Pipe Fittings, etc. 核级设备,如泵、阀门、承压设备、机械模块、电器机柜的应力分析、地震分析和评定。 Stress analysis and seismic analysis of Safety Class Equipments such as pumps, valves, pressure equipments, mechanical modules and the electrical cabinet.

Page 14: Safety aspects of the full life cycle AM

1 核电厂全寿期老化管理的安全性考虑 Safety aspects of the full life cycle AM

阶段

Stage

需求

Needs

围绕需求应开展的活动

Activities arouse from needs

相关技术支撑

Related technical support

制造/建设

Fabricati

on/Manuf

acture

制造阶段充分考虑老化效应

Ageing effects being

sufficiently taken into

account in fabrication

1) 采购方向制造方传递相关要求Conveying ageing related factors to

suppliers by purchaser; 2) 制造时充分 考 虑 老 化 效 应 节 缓 解 措 施 In

fabrication, ageing effects and

related mitigation measures being

sufficiently taken into account; 3)设计方提供技术支持 Designers provide

technical support regarding ageing

analysis

材料性能试验;制造工艺模拟;缺陷评定;容差分析;老化缓解措施

Experiments on material

properties; simulation of

fabrication process; defect

assessment; tolerance

analysis; ageing mitigation

measures

本底数据收集并文档化

Baseline data collection

and documentation

1) 本底数据被规范化地保存并移交采购方 Baseline data being well kept

and submitted to purchaser; 2) 设计

方要对本底数据清单和记录保存提出要求 baseline data list and record

keeping requirements provided by

designer

本底数据技术要求;数据库技术

Baseline specifications;

database technique

根据设计规格书要求留下足够的样品以备日后老化监测评估

Sufficient specimen used

for ageing monitoring and

evaluation based on

design specifications

设计方提出的监督和监测要求应在制造阶段加以落实

Surveillance and monitoring

requirements given in design

specifications by designer and

followed by suppliers

样品监督和使用大纲,例如辐照监督大纲

Specimen program and

utilization plans, such as RPV

surveillance program

Page 15: Safety aspects of the full life cycle AM

1 核电厂全寿期老化管理的安全性考虑 Safety aspects of the full life cycle AM

阶段

Stage

需求

Needs

围绕需求应开展的活动

Activities arouse from needs

相关技术支撑

Related technical support

调试

Commi

ssionin

g

建立老化相关本底数据的测量和保存的系统性大纲

Systematic program as guideline

for measuring and record

keeping for ageing management

related baseline data

在调试期间按大纲要求实施老化相关本底数据的测量和记录保存

In commissioning program, ageing

management related data

measuring and record keeping

requirements should be brought

into and implemented

特殊数据的需求分析;测量和记录保存方法;验收准则

Specific data needed,

methodology on

measurement and record

keeping, acceptance

criteria

特别关注温度和辐射热点的识别以及安全相关系统的管道和转动设备的振动测量

Special attention for

identification of temperature

and irradiation hot spots and for

measurement of vibration on

piping and rotating components

对热点开展系统性探查;开展安全相关系统的管道和转动设备的振动测量;先进的记录保存系统

Systematic investigation on hot

spots; vibration measurement for

safety related piping and rotating

components; advanced record

keeping systems

确定振动限值;建立用于日后趋势分析的本底数据

Identification of vibration

limits; establishment of

baseline for trend

analysis

确认关键工况下的本底数据已按设计要求被测量并很好地保存、现场安装的核安全设备与鉴定条件相一致 Baseline data are properly

collected under critical

conditions which are in

conformance with design

requirements. Installed

equipment is in conformance

with its EQ requirements.

用于安全评审的技术支持性材料;调试期间开展安全相关设备EQ状态的现场再确认

Technical support materials be

ready by operator for safety review;

site reconfirmation being carried

out during commissioning

对鉴定合格的设备开展现场探查,再确认其安装状态和环境条件与鉴定时的假定相一致

For qualified equipment,

carrying out walk down

on site to reconfirm

during commissioning

Page 16: Safety aspects of the full life cycle AM

1 核电厂全寿期老化管理的安全性考虑 Safety aspects of the full life cycle AM

阶段

Stage

需求

Needs

围绕需求应开展的活动

Activities arouse from needs

相关技术支撑

Related technical support

运行Operatio

n

总体性老化管理大纲

Overall AMP

确定AMP策略和开展AMP活动所需要的资源 Determination of

AMP policies and resource

allocation for related activities

系统构筑物部件的筛选;识别或确认老化机理,确定其中的关键因素

SSC screening; ageing

mechanism analysis;

对重要的改造如功率提升、系统更新、设备更换等需要评估老化效应 For any

significant changes,

ageing effects should be

evaluated

应对任何重大改造中老化效应对安全的影响进行评估 Ageing

effects to safety should be

demonstrated for significant

changes

根据工况条件的变化开展时限老化分析,以确保老化问题不至于影响安全

It should be demonstrated by

TLAA that under new conditions

of the changes, ageing effects has

no significant impact to safety.

对新发现的老化效应,应适时开展评估 For any new

discovered ageing

mechanisms, assessment

should be performed in

time

根据现有知识和经验反馈开展老化机理分析 Ageing

mechanism analysis based on

current knowledge and

experience feedback

分析新的老化机理对安全的影响,以确保这种影响能被有效控制

Analyze that the effects to safety

by the new ageing mechanisms

can be effectively controlled

对主要老化机理方面的经验反馈做好预案 Pre-

arranged plan being

prepared based on

experience feedback on

significant ageing

建立针对设备或专题的老化管理分大纲 Establishment and

implementation of component

or topic specific AMPs

各老化管理分大纲应包括老化机理分析、老化评估、老化探测和老化缓解等内容 The AMPs should include

ageing mechanism analysis,

ageing evaluation, inspection,

mitigation, etc.

备品备件管理 Spare parts

management

备品备件的可获得性以及适当的仓储方法 Availability of spare

parts and stock reservation

method

确认更换部件的可获得性

Demonstrate the availability of

replacement parts

Page 17: Safety aspects of the full life cycle AM

1 核电厂全寿期老化管理的安全性考虑 Safety aspects of the full life cycle AM

Degradation Locations

Corrosion Fatigue Irradiation Fretting and

Wear

Core beltline region environment fatigue

neutron irradiation

Stud bolts boric acid corrosion

mechanical and thermal fatigue

Nozzle corner mechanical and thermal fatigue

CRDM penetration PWSCC mechanical and thermal fatigue

Out surface of head boric acid corrosion

Bottom head wear induced by loose parts

Significant ageing mechanisms - Reactor Pressure Vessel

Page 18: Safety aspects of the full life cycle AM

1 核电厂全寿期老化管理的安全性考虑 Safety aspects of the full life cycle AM

Significant ageing mechanisms - Steam Generator

Degradation Sites Erosion-Corrosion

Fatigue Irradiation Fretting

and Wear

Tube to tubesheet crevices ODSCC

Tube to support plate crevices

ODSCC

Sludge pile ODSCC

Free span region of tubes ODSCC

Contact region between tubes and anti-vibration bars

Contact region between tubes and loose parts

fretting-wear

Feedwater nozzle, nozzle to piping welds

erosion-corrosion

high and low cycle fatigue

fretting-wear

Shell girth welds SCC Corrosion-fatigue

Feedwater nozzle bore, blend radius, shell inside surface beneath the nozzle

high-cycle fatigue

J-tubes and feedring erosion-corrosion

Page 19: Safety aspects of the full life cycle AM

1 核电厂全寿期老化管理的安全性考虑 Safety aspects of the full life cycle AM

Degradation Sites Erosion-Corrosion

Fatigue Irradiation Fretting and

Wear

Core barrel thermal

stress, FIV neutron

irradiation

Formers and baffles Thermal stress

irradiation swelling

Bottom-mounted instrumentation

FIV fretting wear

Guide tube assembly FIV fretting wear

Radial keys FIV fretting wear

Instrumentation sleeve, control rod guide tube

FIV wear

Irradiation surveillance capsule

FIV neutron

irradiation fretting wear

Connections (bolts, pins)

IGSCC,

IASCC FIV

irradiation creep and swelling

Compressed elastic ring

Axial forces

Significant ageing mechanisms - Reactor Internals

Page 20: Safety aspects of the full life cycle AM

1 核电厂全寿期老化管理的安全性考虑 Safety aspects of the full life cycle AM

Significant ageing mechanisms - other primary loop components

Component Erosion-Corrosion

Fatigue Embrittlement Fretting

and Wear

Pressurizer (spray nozzle)

thermal fatigue

RCP (rotating parts) vibration

Charging pump (rotating parts)

vibration

Pressurizer safety valve

thermal stratification

thermal ageing of CF8M material

mechanical vibration

Electric gate-valve thermal stratification

thermal ageing of CF8M material

mechanical vibration

Main piping thermal/ mechanical fatigue

thermal ageing

Surge line of pressurizer

thermal/ mechanical fatigue

Vibration

Class 1E Cable oxidation and chemical corrosion

thermal ageing/ irradiation embrittlement

vibration

transformer cyclic operation thermal ageing

Page 21: Safety aspects of the full life cycle AM

1 核电厂全寿期老化管理的安全性考虑 Safety aspects of the full life cycle AM

Significant ageing mechanisms - Containment and structures

Structures Corrosion Fatigue Embrittlement Concrete

degradation

Concrete acidic or alkaline corrosion

fatigue Leaching and efflorescence

Reinforced concrete

General corrosion or pitting of reinforced steel

Temperature increase near reactor cavity

Pre-stressing system

Denting, stress corrosion or hydrogen embrittlement

Loss of prestressing

Steel lining Corrosion induced by anti-rust failure

Page 22: Safety aspects of the full life cycle AM

1 核电厂全寿期老化管理的安全性考虑 Safety aspects of the full life cycle AM

阶段

Stage

需求

Needs

围绕需求应开展的活动

Activities arouse from needs

相关技术支撑

Related technical support

退役

Decommis

sioning

通过老化管理保证退役活动有效开展

Decommissioning

activities should

be carried out

through effective

ageing

management

对退役活动所需要的系统、构筑物和部件保持可用和功能完好

SSCs important to

decommissioning should be

maintained their availability

and functionality through

effective ageing management

分析系统、构筑物和部件保持功能的能力

Analyze functionality of

aged SSCs which are

important to

decommissioning

Page 23: Safety aspects of the full life cycle AM

1 核电厂全寿期老化管理的安全性考虑 Safety aspects of the full life cycle AM

- 新的挑战 New Challenges

新挑战体现于 New

challenges reflect in:

设计理念 Design

设备制造 Manufacture

设备鉴定 EQ

建造调试 Construction

and Commissioning

营运管理 Operation

检查维修 Maintenance

执照取证 Licensing

不同阶段之间互有关联 Different stages

have relations from each other :

设备鉴定要求状态监测,引入QLD的概念

EQ introduces OLD which requires

condition monitoring

运行阶段的老化管理依赖于设计建造阶段

的资料

AM in operation deeply depends on data in

design and manufacture stages

需要有系统性、全局性的考虑

Systematic and overall considerations

Page 24: Safety aspects of the full life cycle AM

1 核电厂全寿期老化管理的安全性考虑 Safety aspects of the full life cycle AM

-管理挑战 New Challenges in Management

- 尽管终极责任属于业主,但各阶段的责任如何分解?Although ultimate

responsibilities belong to utilities, how to distribute them to related parties?

可靠性Reliability

设计 Design

采购 Procurement

制造 Manufacture

安装Installation

调试Commissioning

运行Operation

设计院Designer

业主/工程公司Utilities /

Eng. Comp.

供应商Vendors

安装公司Installation

Comp.

业主/工程公司/服务商

Utilities/ Eng.

Comp./

Services

业主/营运者/服务商Utilities / Operator /

Services

Page 25: Safety aspects of the full life cycle AM

25

二. 核电厂寿命管理的经济性考虑

II. Economic considerations for life management of NPPs

Page 26: Safety aspects of the full life cycle AM

26

二. 核电厂寿命管理的经济性考虑

Economic considerations for life management of NPPs

老化管理(AM):将老化过程控制在可接受的限度内的工程、

运行和维护行为。

Ageing Management (AM) :Practice in engineering,

operation and maintenance to control the ageing of

NPPs’ SSCs in acceptable extends

寿命管理 (PLiM) : 老化管理和经济性考虑的合成。

Life management (PLiM) : Combination of ageing

management and economic considerations.

Page 27: Safety aspects of the full life cycle AM

27

二. 核电厂寿命管理的经济性考虑

Economic considerations for life management of NPPs

核电厂寿命管理的目标在于 The targets of NPP PLiM lie in:

维持高的安全水平 Maintaining high safety level

优化SSCs运行、维护和使用寿命 Optimizing SSCs’ operation,

maintenance and service life

维持可接受的性能状态 Maintaining acceptable SSCs’

performance status

在超过电厂寿期的条件下,追求最大限度的投资回报 Obtaining

as much as possible the return on investment beyond NPP

lifetime

为电厂长期运行创造条件 Establish basis for LTO of NPP

Page 28: Safety aspects of the full life cycle AM

28

二. 核电厂寿命管理的经济性考虑

Economic considerations for life management of NPPs

全部电厂设备

All NPP Eq.

安全重要设备

Safety related Eq.

电厂寿命相关设备

PLiM related Eq.

其他设备

Other Eq. 安全重要设备中被推荐作老化研究的设备

AM related Eq.

among safety

related Eq.

寿命管理设备的范围比老化管理的大

The Scope of PLiM is larger than that of AM

Page 29: Safety aspects of the full life cycle AM

29

二. 核电厂寿命管理的经济性考虑

Economic considerations for life management of NPPs

核电厂寿命管理 PLiM

老化管理

AM 资产管理 Asset Mgm

知识管理

KM

寿命评估

Life Evl.

经济性评估

Economic

Assessment

运行许可证延续

OLE

核电厂老化管理与寿命管理的关系

老化管理 (AM):

从安全角度考虑 More

focus on safety

范围限于安全相关SSCs

Limited in safety related SSCs

寿命管理 (PLiM):

兼顾经济性从全厂范围考虑

Economic, more from whole

plant

范围更广,包括二回路 2nd

Loop included

资产管理 Asset Mgm.

知识管理 KM

Page 30: Safety aspects of the full life cycle AM

二. 核电厂寿命管理的经济性考虑

Economic considerations for life management of NPPs

国际原子能机构成立了核电厂寿命管理技术工作组 IAEA TWG-LMNPP

Engineering

Support

Nuclear

Materials Aging

& Degradation

Maintenance

and Safety/

Risk

Programmatic

Issues on PLiM

Information

Processing &

Efficiency

Improvement

Support

Expansion and

New comers

(30%)

• RPV

• Ageing

Management

• Concrete

• Cabling

• Buried Piping

• Mitigation

Technologies

• Maintenance

• Outage

Management

• Reliability of

Components

• NDE/ISI

• DMW

• PLiM Model

• Economics of LTO

• Equipment Qualification

• Power uprates

• Severe Accident

Management

• PRIS

• CNPP

• Performance

• Pre-construction

& Management

• Feasibility Study

• TSO

• Design Review

• Construction

• Procurement

• Grid reliability

• Flexible

Operation

Operating NPPs and

Expanding Programme

International Organizations

• OECD-NEA

• EC-JRC

• WANO

• National

Organizations

(INPO, MSs)

Page 31: Safety aspects of the full life cycle AM

二. 核电厂寿命管理的经济性考虑

Economic considerations for life management of NPPs

IAEA TWG-LMNPP 2015年会议上确定的优先主题 topics concerned by IAEA

2016~2017年度(高优先级/High

priority)

2016~2017年度(中优先级/ Middle

priority)

严重事故管理导则(正常运行和停堆低功率)(SAMG)

压水堆一回路和二回路水环境下环境促进疲劳的评估方法研究 (EAC problems)

备品备件优化模型开发 (Optimization of

spare parts) 考虑长期运行效应的反应堆压力容器材料辐照脆化和热老化监测 (RPV embrittlement)

长期运行项目管理 (Project management

of LTO) 二回路水化学控制 (Water chemistry 2nd loop)

异种金属焊接检查、监测和修复技术研究 (DMW)

退役过渡阶段的寿命管理 (Life management

for decommissioning)

设计基准事故及超设计基准事故下的设备鉴定 (EQ under DBA and BDBA)

基于极端事故的经验反馈对当前核电厂长期运行的反思 (Reconsideration of LTO policies)

来自SALTO的经验反馈 (Experience

feedback from SALTO) 生物腐蚀问题 (Bio corrosion)

仪电设备可靠性和老化管理导则 (Guidelines of reliability and AM for EI&C)

超前主动的材料退化问题分析:识别知识、研发与需求之间的缺口 (Material R&D)

来自数字化仪控更新改造的经验反馈 (Experience feedback from digital

renovation)

用IT技术开展配置管理(CM using IT

technology)

Page 32: Safety aspects of the full life cycle AM

二. 核电厂寿命管理的经济性考虑

Economic considerations for life management of NPPs

IAEA TWG-LMNPP 2015年会议上确定的优先主题 topics concerned by IAEA

2018~2019年度

高辐照材料焊接修复方法研究 (Welding repair under high irradiation)

反应堆压力容器辐照脆化问题 (RPV

embrittlement issues)

结构和设备老化退化预测模型 (Ageing

degradation prediction models)

用于确定堆内构件关键部件中子辐照肿胀无损探测方法 (Methods of NDT

identification of swelling in critical parts

of RVI)

先进的混凝土结构检查和修复方法 (Advanced methodologies for concrete

structure inspection and repair)

Page 33: Safety aspects of the full life cycle AM

三.SNPTC的实践

III SNPTC’s Practice

Page 34: Safety aspects of the full life cycle AM

SNPTC的实践 SNPTC’s practice

国核核电设备与材料鉴定咨询中心建设

Establishment of SNEQC

Page 35: Safety aspects of the full life cycle AM

国核核电设备与材料鉴定咨询中心建设

Establishment of SNEQC

2.5m*2.5m三轴六自由度抗震台

1.5m*1.5m电磁振动台

SNPTC的实践 SNPTC’s practice

Page 36: Safety aspects of the full life cycle AM

国核核电设备与材料鉴定咨询中心建设 Establishment of SNEQC

图1-LOCA台架实物图 图2-LOCA试验控制室

LOCA试验装置

大:24立方米

最大温升速率不小于130℃/s 中:14.7立方米

小:7.1立方米

SNPTC的实践 SNPTC’s practice

Page 37: Safety aspects of the full life cycle AM

国核核电设备与材料鉴定咨询中心建设 Establishment of SNEQC

图-高温蠕变持久试验设备实物图

• EQ中心配备210多台套材料力学和微观组织分析试验设备,具备开展高温力

学、蠕变、持久、松弛、蠕变/蠕变-疲劳裂纹扩展、蠕变-疲劳交互作用、复

杂载荷疲劳、疲劳裂纹扩展、断裂韧性和高分辨率微观组织分析等试验能力。

SNPTC的实践 SNPTC’s practice

Page 38: Safety aspects of the full life cycle AM

CAP系列核电站电气贯穿件是由上海发电设备成套设计研究院开发的新一

代核电贯穿件,目标是用于后续CAP1000和1400示范工程。

2013.4.27

2013.12

•鉴定大纲专家评审会

• EMC及预处理试验完成

• LOCA试验完成

2014.3

• 电气短路试验完成

2014.4

• 抗震试验完成

2015.1

2015.3

• 鉴定项目完工

CAP系列电气贯穿件鉴定 EQ for EPA of CAP series NPPs

SNPTC的实践 SNPTC’s practice

Page 39: Safety aspects of the full life cycle AM

典型阀门的EQ实践 EQ practice typical valves

受苏阀、大高等委托,开展CAP系列关键阀门鉴定活动 Key Valves:

conducting qualification activities of CAP series squib valve for SUFA, DV

VALVE and CSIC

CAP1400主蒸汽安全阀鉴定 、CAP1400 1E级直流执行机构鉴定CAP1400 main steam safety valve qualification; CAP series class 1E DC

actuator qualification.

SNPTC的实践 SNPTC’s practice

Page 40: Safety aspects of the full life cycle AM

电磁阀的抗震裕度试验

The Seismic margin test for electric-magnet valve

设备鉴定基础性研究

R&D on EQ fundamental aspects

非金属材料的活化能测定

The activation energy measurement for non-metallic

material

SNPTC的实践 SNPTC’s practice

上海核工院实施 -

Implemented by SNERDI

Page 41: Safety aspects of the full life cycle AM

基准考题、状态监测 Benchmark, CM

• 热老化 Thermal

• 辐照老化 Radiation

• 热-辐照交互 Thermal-Radiation

Irradiation Cell (AECL) Irradiation Thermobox (UJV)

Thermal (AMS and others)

IAEA电缆老化探测协作研究项目 IAEA CRP on cable ageing study

SNPTC的实践 SNPTC’s practice

上海核工院实施 -

Implemented by SNERDI

Page 42: Safety aspects of the full life cycle AM

SNPTC的实践 SNPTC’s practice

秦山压水堆机组堆内构件老化管理大纲开发

Reactor Internals AMPs development for PWRs of Qinshan NPP

Qinshan-II 4 x 650

MWe PWR units Qinshan-I 1 x 320

MWe PWR unit

Entrusted by CNNO, SNERDI carried out AMP development for Qinshan-I

and Qinshan-II (2013~2015) 上海核工院实施 -

Implemented by SNERDI

Page 43: Safety aspects of the full life cycle AM

SNPTC的实践 SNPTC’s practice

老化机理评估 Evaluation

on RI ageing mechanisms Fatigue

Irradiation

embrittlement

Wear

Stress relaxation

Stress corrosion

cracking (SCC)

Irradiation-assisted

stress corrosion

cracking (IASCC)

Void swelling

Thermal ageing

embrittlement

上海核工院实施 -

Implemented by SNERDI

秦山压水堆机组堆内构件老化管理大纲开发

Reactor Internals AMPs development for PWRs of Qinshan NPP

Page 44: Safety aspects of the full life cycle AM

SNPTC的实践 SNPTC’s practice

秦山压水堆机组主系统管道老化管理研究 上海核工院实施 PWR Primary Boundary Piping System AM Research for Qinshan NPP

-- Qinshan-I and Qinshan –II, carried out by SNERDI

Ageing Mechanism Analysis

Aging Condition

Assessment Guide Line

Structure of AM Data Base

Aging Condition Evaluation

and Remaining Life

Evaluation

Primary Boundary Piping

System AMP -- General

Primary Boundary Piping

System AMP – Unit Specific

Technical Guideline for

Primary Boundary Piping

System AM Evaluation

主要任务 Main tasks:

Page 45: Safety aspects of the full life cycle AM

SNPTC的实践 SNPTC’s practice

• Examples of AM

Analysis

– Thermal Ageing

– PWSCC

上海核工院实施 -

Implemented by SNERDI

秦山压水堆机组主系统管道老化管理研究 PWR Primary Boundary Piping System AM Research for Qinshan NPP

Page 46: Safety aspects of the full life cycle AM

SNPTC的实践 SNPTC’s practice

• 老化状况分析举例 Examples of

Ageing Condition Analysis

– 热分层 Thermal

Stratification

– 裂纹扩展 Crack Growth

– 疲劳 Fatigue

Analysis model

Stress analysis

Loading match

Fatigue Evaluation

上海核工院实施 -

Implemented by SNERDI

秦山压水堆机组主系统管道老化管理研究 PWR Primary Boundary Piping System AM Research for Qinshan NPP

Page 47: Safety aspects of the full life cycle AM

SNPTC的实践 SNPTC’s practice

大亚湾堆外中子注量实测 Daya Bay NPP Ex-Vessel Neutron Dosimetry

The Ex-Vessel Neutron Dosimetry

(EVND) was installed in one of units

of Daya Bay NPP in October 19th

2013

Data from EVND provide best

estimation of RPV neutron exposure

together with data from RPV

surveillance capsules and

calculated neutron fluence, which

can be used in following aspects:

Assess the neutron

embrittlement of RPV

monitor the change of

neutron fluence rate and

spectrum after modification of

core design and reactor

internals

Provide data for RPV aging

management and life extension

of NPP

Crew of EVND installation in Daya Bay NPP

国核运行实施 - Implemented

by SNPSC

Page 48: Safety aspects of the full life cycle AM

SNPTC的实践 SNPTC’s practice

核电常规岛寿命管理 Life management for conventional island

Equipment Supervision

Pfm.

tests

Monitoring on vib., stress and pfm.

Metal

supervision and

failure analysis

Life

mgm.

R&D

topical

projects

Sys. upgrading Eq. upgrading Maint. support

Overall Target:Digital plant, good economy, high reliability, good

safety performance and well under control

上海成套院实施 - Implemented by SPERI

Page 49: Safety aspects of the full life cycle AM

SNPTC的实践 SNPTC’s practice

秦山核电厂OLE技术支持 TS on OLE for Q1

2013 2014 2015 2017 2020 2021 2016

R18(2018.4~2019.4) R19、R20

2021.12

获得延照运行执照

OLE

permission

制定技改总体计划 Integrated schedule

establishment

上海核工院实施 - Implemented by SNERDI

Page 50: Safety aspects of the full life cycle AM

结语 Summary

核电厂老化管理涉及其生命周期的各阶段,为核电厂从一开始就处于安全、可靠状态提供支撑

Ageing management covers all stages of the full life of NPPs,

providing sound support to safe and reliability of NPPs from very

beginning.

核电厂寿命管理的范围更大,不仅要关注安全性,还要考虑经济性

PLiM covers larger scope, not only including safety aspects, but

also including economic aspects.

国家核电技术公司各下属单位致力于发挥各自优势,为核电厂生命周期各阶段的安全性、经济性提供全方位服务

Organizations under SNPTC is doing their best to provide

comprehensive services to NPPs and vendors to ensure safety

and economy for all stages of NPPs.

Page 51: Safety aspects of the full life cycle AM

谢谢关注!

Thanks for your attention!