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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
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
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
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.
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
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
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
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
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
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
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
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
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.
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
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
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
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
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
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
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
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
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
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
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
25
二. 核电厂寿命管理的经济性考虑
II. Economic considerations for life management of NPPs
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.
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
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
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
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)
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)
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)
三.SNPTC的实践
III SNPTC’s Practice
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
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
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
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
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
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
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
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
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
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
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:
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
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
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
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
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
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.
谢谢关注!
Thanks for your attention!