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Strategy Maps 2007 for Ageing ManagementStrategy Maps 2007 for Ageing Management
Naoto Sekimura, Prof., Dr. Department of Quantum Engineering and Systems ScienceDepartment of Nuclear Engineering and Management
The University of Tokyo
IAEA IAEA PLiMPLiM 2007 Symposium 2007 Symposium Shanghai, China, October 15Shanghai, China, October 15--18, 200718, 2007
Technical cooperation among research organizations,Technical cooperation among research organizations,utilities and Universitutilities and Universitiesies in Japanin Japan-- Infrastructure for Ageing Management Infrastructure for Ageing Management --
-- Domestic and International Research Cooperation Domestic and International Research Cooperation ---- Database and Information Basis, Human Resources Database and Information Basis, Human Resources --
Technical Information Base
Comprehensive coordination
Industry � Technical development� Plant information, etc.
Academia
�Basic research �Scientific information, etc.
Government
� Safety research � Information on regulations,
etc.
Umbrella NetworkInformation Exchange
Other Industries
International Projects
A Coordinating Committee on Ageing ManagementA Coordinating Committee on Ageing Managementwas established with members from industries, utilities,
research organization and regulatory authorities.
2
R&D Roadmaps for Ageing ManagementR&D Roadmaps for Ageing Managementand Safe Long Term Operationand Safe Long Term Operation
developed by Atomic Energy Society of Japan in 2004developed by Atomic Energy Society of Japan in 2004--20052005
Database onRegulationProceduresIn OtherCountries
To Keep Safety and Reliability of Nuclear Power PlantsTo Keep Safety and Reliability of Nuclear Power Plantsfor Long Term Operationfor Long Term Operation
EstablishmentEstablishmentof Informationof Information
BasisBasisTechnicalTechnical
DevelopmentDevelopment Codes andCodes andStandardsStandards
SystematicSystematicMaintenanceMaintenance
SystematicAgeing
ManagementProgram
Database forDegradation of
Materials
RPVRadiationEmbrittle-lment
EvaluationEvaluationTechnologyTechnology
for Degradationfor Degradationof Componentsof Components
PerformanceIndex
SchemesTo ApplyNew
Techniques
Standardization ofStandardization ofAgeing ManagementAgeing Management
ProceduresProcedures
HumanResources
Risk-basedMaintenance
Optimization ofOptimization ofMaintenanceMaintenance
IASCC
1.1. 2.2. 3.3. 4.4.
3
Development of Development of Technical Information InfrastructureTechnical Information Infrastructure
Human Resources
Technical Information Infrastructure
SystematicMaintenanceImprovement
Development of Codes and Standards
Selection of Research Theme
Research result
-Maintenance Information -Case Maintenance -Operating Experience
Latest Information
Tacit Knowledge Tools for Education
Latest Information
Technical Evaluation Result
4
Safety Research & Development
Strategy of Safety Research and Related Strategy of Safety Research and Related Infrastructure for Ageing Management Infrastructure for Ageing Management
Ageing technical information databasePlant operation experience database
Technical information networkKnowledge management system
Regulatory System Infrastructure
BudgetSupport
FacilityInfrastructure
HumanResources
Codes and Standards
Maintenance Engineering of Plant Systems
Technological Information Infrasturcture
SafetyResearch
5
- Strategic training of expertise human resources
- international cooperation
R&D Roadmaps for Ageing ManagementR&D Roadmaps for Ageing Managementand Safe Long Term Operationand Safe Long Term Operation
developed by Atomic Energy Society of Japan in 2004developed by Atomic Energy Society of Japan in 2004--20052005
Database onRegulationProceduresIn OtherCountries
To Keep Safety and Reliability of Nuclear Power PlantsTo Keep Safety and Reliability of Nuclear Power Plantsfor Long Term Operationfor Long Term Operation
EstablishmentEstablishmentof Informationof Information
BasisBasisTechnicalTechnical
DevelopmentDevelopment Codes andCodes andStandardsStandards
SystematicSystematicMaintenanceMaintenance
SystematicAgeing
ManagementProgram
Database forDegradation of
Materials
RPVRadiationEmbrittle-lment
EvaluationEvaluationTechnologyTechnology
for Degradationfor Degradationof Componentsof Components
PerformanceIndex
SchemesTo ApplyNew
Techniques
Standardization ofStandardization ofAgeing ManagementAgeing Management
ProceduresProcedures
HumanResources
Risk-basedMaintenance
Optimization ofOptimization ofMaintenanceMaintenance
IASCC
1.1. 2.2. 3.3. 4.4.
6
Continuous Revision of Strategy MapsContinuous Revision of Strategy Maps forforAgeing Management by All the StakeholdersAgeing Management by All the Stakeholders
①①①①Introduction Scenario
②②②②Maps of Technical Issues
Strategy Maps for Ageing ManagementStrategy Maps for Ageing Management
Nuclear Safety Regulatory Standard Committee in NISA
Comments &Participation
Periodic Revision through Latest Knowledge
……
………
……
Publicity
• Needs• Targets• Milestones
• R&D projects• Information Basis• Hardware Resources• Human Resources
Safety Research Sub-Committee inthe Coordinating Committee on Ageing Management
Publication
2006 2006 --
③③③③Roadmaps
• Budgetary Actions forResearch and Infrastructure
• Regulation Systems withCodes and Standards
7
Major Roles of Industries, Government and Major Roles of Industries, Government and Academia for Ageing ManagementAcademia for Ageing Management
・・・・To develop, review strategy maps periodically and build a consensus with experts from industries, government and academia
by identifying important issues to be solvedby discussing roles of stakeholders for rational and efficient implementation of research
・・・・To develop and improve codes and standards based on safety research outcome
Academic Societies
• Responsibility to establish and improve safety regulations - by conducting safety researches, - by keeping infrastructure • Responsibility to promote nuclear energy for national energy security
Government
・Responsibility to contribute to safety research activities- to accumulate and expand fundamental knowledge- to keep human resources through the safety research
Academia
• Primary responsibility to keep safe operation of power plants
- research and development, and development of the infrastructure for safety and public interests
Industries
8
4. Systematic MaintenanceSystematic Maintenance3. Establishment of Information Basis3. Establishment of Information Basis
2. Establishment of Codes and Standards2. Establishment of Codes and Standards1. Safety Research to Solve Ageing Issues1. Safety Research to Solve Ageing Issues
* Advanced designs will be developed based on past operating experience.
* Predication methods and monitoring technology will be upgraded.
* Countermeasures are being taken by rule of thumb based on plant data.
Irradiation embrittlement
* Simulation methods will be established. * ISI technology will be upgraded.
* Use of SCC-resistant materials will be ensured. * Database will be constructed.
* Countermeasures suited to materials in use are being taken. * Database is being constructed.
Stress corrosion crack
* Past records of performance will be reflected in the maintenance technology and durability designs for new plants. * Recycling methods will be established for replaced structures and materials.
The reliability of integrity evaluation methods will be improved or enhanced. CCV integrity evaluation methods will be established.
Intensive study is being made on scarcely known fields.
Decreased strength of concrete
* Monitoring technology will be upgraded.
Deterioration diagnosis technology will be upgraded.
* Countermeasures suited to materials in use are being taken. * Database is being constructed.
Deteriorated cable insulation
* Monitoring technology will be upgraded.
* Mechanism-based predication methods will be established. * Risk-based maintenance methods will be established.
* Countermeasures suited to materials in use are being taken, and database is being constructed. Wall thinning
* Countermeasures suited to materials in use or environment will be taken, and database will be constructed.
* Countermeasures suited to materials in use or environment will be taken, and database will be constructed.
* Countermeasures suited to materials in use or environment are being taken, and database is being constructed. Fatigue
Long-life, next-generation reactor 40th to 50th year Current StatusAging
phenomenon
Strategy Maps 2007 for Ageing ManagementStrategy Maps 2007 for Ageing ManagementMaps for Technical IssuesMaps for Technical Issues
9
Strategy Maps 2007 for Ageing ManagementRoadmaps for Stress Corrosion CrackingRoadmaps for Stress Corrosion Cracking
10
Aps
Phase I (until 40 year operation of early stage NPPs2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015~~~~2019 2020~~~~2029
Phase II (until 50 year operation) Phase III (until 60 year operation)Fiscal Year
Preparation and refinement of initiation data and crack growth data on IASCC
Preparation of infrastructure for IASCC research Preparation and refinement of initiation data and crack growth data on IASCC Confirmation of the data and evaluation technology, and preparation of regulatory criteria
Understanding of IASCC mechanism
Simulation technology of IASCC initiation and propagation
Establishment of code and standards, and regulatory criteria
IASCC initiation test methods
Refurbishment of laboratory facility including JMTR
Extended IASCC crack initiation data and its refinement
Extended IASCC crack growth data and its refinementCorrelation between laboratory data and field events
Obtaining of crack growth data for ex-plant materials In-core IASCC Initiation and growth evaluation
IASCC evaluation technology confirmation Understanding and modeling of IASCC crack
Study of accelerated irradiation validity
Understanding and modeling of IASCC crack initiation and growth mechanism
Development of simulation technology of IASCC initiation and growth
Study of IASCC mechanism at high fluence region
Establishment of CS for fitness-for-service
IASCC integrity evaluation guide
Establishment of CS for fitness-for-serviceCoding of IASCC initiation and growth simulationSCC long term integrity evaluation guide
Establishment of code and standards, and regulatory criteria
1. Integrity Evaluation : IASCC1. Integrity Evaluation : IASCC2. Integrity Evaluation : IGSCC2. Integrity Evaluation : IGSCC
3. Integrity Evaluation : 3. Integrity Evaluation : NiSCCNiSCC4. Inspection Technologies on SCC4. Inspection Technologies on SCC
5. Monitoring Technologies on SCC5. Monitoring Technologies on SCC6. Repair & Replacement Technologies6. Repair & Replacement Technologies
Strategy Maps 2007 for Ageing ManagementRoadmap of Research and of Code Development for IASCCRoadmap of Research and of Code Development for IASCC
Phase I (until 40 year operation of early stage NPPs2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015~~~~2019 2020~~~~2029
Phase II (until 50 year operation) Phase III (until 60 year operation)Fiscal Year
Preparation and refinement of initiation data and crack growth data on IASCC
Preparation of infrastructure for IASCC research Preparation and refinement of initiation data and crack growth data on IASCC Confirmation of the data and evaluation technology, and preparation of regulatory criteria
Understanding of IASCC mechanism
Simulation technology of IASCC initiation and propagation
Establishment of code and standards, and regulatory criteria
IASCC initiation test methods
Refurbishment of laboratory facility including JMTR
Extended IASCC crack initiation data and its refinement
Extended IASCC crack growth data and its refinementCorrelation between laboratory data and field events
Obtaining of crack growth data for ex-plant materials
In-core IASCC Initiation and growth evaluation
IASCC evaluation technology confirmation Understanding and modeling of IASCC crack
Study of accelerated irradiation validity
Understanding and modeling of IASCC crack initiation and growth mechanism
Development of simulation technology of IASCC initiation and growth
Study of IASCC mechanism at high fluence region
Establishment of CS for fitness-for-serviceIASCC integrity evaluation guide
Establishment of CS for fitness-for-service
Coding of IASCC initiation and growth simulationSCC long term integrity evaluation guide
Establishment of code and standards, and regulatory criteria
11
10⑨
1714130908
T1
2F1 K4SK1
Tsu22F20
O11F5
2
1F2⑦⑦⑦⑦
8
242322212019181615121110070605040302012000Year
O2K2TM11F42F41F3T4OG12F21F1Tsu11F61F4①①①①
1F3T21F2①①①①①①①①
Tsu1
I3K3M2GN2M1O1To2H3M32F3SD1M2②②②②②②②②
O2To2M3②②②②
T1②②②②
3
OG1④④④④④④④④④④④④
O2④④④④④④④④
SD21F2④④④④
5
SD1⑤⑤⑤⑤
GN1T16
9
GN3
2F2
SM1
O4
H4
I2
③③③③
TM2
1F1
K5
Tsu1
SM2
1F6
1F5
H2I1
H1
③③③③
T3
K1
T2
SM1
⑥⑥⑥⑥
I2
③③③③
GN2M1
③③③③
H2
GN10
M21F1M1 I1H1SM11
③③③③③③③③
4
7
⑨⑨⑨⑨
12
Strategy Maps 2007 for Ageing ManagementScenarios(1)
-- Ageing Management Technical Evaluation for Every 10 Years Ageing Management Technical Evaluation for Every 10 Years --•• Increase in number of plantsIncrease in number of plants•• From initial plants to standardized plantsFrom initial plants to standardized plants
First plant to exceed 40 years of operation
First plant to exceed 50 years of operation
Note: This figure is drawn assuming that all of the plants currently in service will continue their operation.
99 00 01 02 03 04 05 06 07 08
2004-2006
1996-2003
Assessment of Cable Aging for NuclearPower Plant (ACA)
2003-2007
Evaluation Methodology of Crack GrowthRate for Ni-based Alloys (NISCC)Evaluation of Irradiation Assisted StressCorrosion Cracking (IASCC)
1997-2010
Nondestructive Inspection Technologies forthe Narrow Penetrations on Reactor Vessel(NPV)
2005-2008
2005-2009
Development of Seismic Safety EvaluationMethod on Aged Nuclear Facilities
2002-2008
2001-2007
Nondestructive Inspection Technologies onNi-based Alloy Welded Joint (NNW)
Nuclear Power Plant Material ImprovementTechnology (PMT)
Repair Welding Technology of IrradiatedMaterials (WIM)
Intergranular Stress Corrosion Cracking ofNuclear Grade Stainless Steel (IGSCC)
Nondestructive Inspection Technologies forCore Shroud Integrity Assessment (NSA)
2003-2006
2002-2008
Category
2000-2008
Priods
1996-20091994-2006
JFY
Assessment of concrete Aging for NuclearPower Plant
Nuclear Power Plant Integrated ManagementTechnology (PLIM)
2000-2009
Environmental Fatigue Tests of NPPMaterials for Reliability Verification (EFT)Integrity Assessment of Flawed Componentswith Structural Discontinuity (IAF)
Major Projects
Agein
g Eva
luatio
nIns
pecti
on
and
Monit
oring
Evalu
ation
of SC
C
Maint
e-na
nce&
Re
pair
JNES Projects for Ageing Management JNES Projects for Ageing Management Sa
fety R
esea
rch on
evalu
ation
of N
PPSe
ismic
safet
y
13
100 1000 10000 1000000
100
200
300
400
500
80oC-3Gy/h 90oC-3Gy/h 100oC-3Gy/h 80oC-18Gy/h 90oC-18Gy/h 100oC-18Gy/h 80oC-100Gy/h 90oC-100Gy/h 100oC-100Gy/h
Elong
ation
at br
eak (%
)
Time (hours)
Simultaneous aging characteristics of the FR-EPR insulator (black core) made by A company
100 1000 10000 1000000
100
200
300
400
500
600
80oC-3Gy/h 90oC-3Gy/h 100oC-3Gy/h 80oC-18Gy/h 90oC-18Gy/h 100oC-18Gy/h 80oC-100Gy/h 90oC-100Gy/h 100oC-100Gy/h
Elong
ation
at br
eak (%
)
Time (hours)
Simultaneous aging characteristics of the XLPE insulator made by A company
Examples of the results obtained from ACA projectExamples of the results obtained from ACA project
� Progress of degradation may be significantly different among various manufacturers, even for the same kind of insulator. � There were some cables that indicated significantly rapid progress of
degradation at low dose during simultaneous aging, and many other cables also indicated relatively rapid progress of degradation during simultaneous aging.
Major results obtained from ACA project
14
Elong
ation
at Br
eak (
%)
Elong
ation
at Br
eak (
%)
Time (hrs) Time (hrs)
PLM research promotion council board 【【【【Policies regarding research promotion】】】】
[[[[Secretariat: JANTI (FEPCO)]]]]
PLM research administrative review meeting
【【【【Discussing research strategies】】】】[[[[Secretariat: CRIEPI]]]]
10 Sub Group (SG): Examination team【【【【Individual Issues.】】】】
Providing future directionsEvaluation results
Industrial Efforts to Promote PLMIndustrial Efforts to Promote PLM--related R&D Activities *related R&D Activities *
<<<<Electric power companies, manufacturers and organizations that are involved in the support system>>>>
Nine electric power companies, JAPC, Electric Power Development CO., CRIEPI and JANTI
Technology information coordination committee
Collaboration
Collaboration
Nuclear energy development committee Comprehensive
task force
Nuclear energy development committee
Equipment maintenance committee
<<<<The Federation of Electric Power Companies of Japan>>>>
Chairman and deputy chairman of promotion council board participate in the committee.
15
* * KamadaKamada et al; this Symposiumet al; this Symposium
Research ProjectResearch Project on Fundamentals ofon Fundamentals ofAgeing ManagementAgeing Management (NISA funds)(NISA funds)
General Review Session on Ageing Management Infrastructure Improvement
Review Session on Ageing Management Database and Knowledge Base Review Session on Seismic Effects on Piping ThinningReview Session on Condition Monitoring and Safety Preservation Technology Review Session on Irradiation Embrittlement
Review Session on Cable Degradation
Review Session on Stress Corrosion Cracking
Tohoku ClusterICR
Fukui ClusterINSS
East Japan Cluster
MRI
Ibaraki ClusterJAEA
General Review Session WG
InformationExchange
ProgressReportAdvice
ProgressReportAdvice
TechnicalInformationCoordinationCommitteeSafety ResearchWGIn JNES
Outcome
NISA (Nuclear and Industrial Safety Agency) in METI
Academic Societies etc.
InformationExchange
16
Development of New Embrittlement CorrelationDevelopment of New Embrittlement Correlation
• Fundamental study on the embrittlement mechanisms– Nano-structural characterization by experiments– Multiscale computer simulation of microstructural evolution
• Mechanism-guided embrittlement correlation– Surveillance data in Japan– New approach using rate equations in predicting microstructural changes
17
Hierarchical Structure of Degradation ofHierarchical Structure of Degradation ofMaterials for Light Water ReactorsMaterials for Light Water Reactors
Effects of Radiation in Nuclear Materials and Effects of Radiation in Nuclear Materials and Ageing Management of Nuclear SystemsAgeing Management of Nuclear Systems
Radiation Damage ProcessesRadiation Damage Processes
Evaluation MethodologiesEvaluation Methodologies
Nuclear Reaction
Phase10 sec
-13
10 sec
-11
10 sec
-6
M onte-C arlo
Sim ulation
10 sec
9
10 sec
-3
10 sec 10 sec
14~7
Collisional Phase
Cooling Phase
Thermal Phase
Diffusional Phase
Micro- structure
Property Changes
Lifetime Optimization
Binary Collision Approximation
Molecular Dynamics
Analytical Diffusion & Reaction Rate Equations
Dislocation Dynamics
Finite Element Method
Post Irradiation Tests
System Maintenance, Safety, Reliability Economy
Single CascadeMultiple Cascades, Subcascades Cascade Clusters,
Migrating DefectsNucleation and Growth of Defect Clusters
Volume Change, Strength, Creep, Fatigue, Corrosion, Crack Initiation & Growth ....
10 sec
-15
NPRIM Code
Primary Knock-on Atom
Nuclear Reaction
Phase
N. Sekimura (1994)18
MultiMulti--scale Computer Simulationscale Computer SimulationMolecular DynamicsDislplacement cascade
Kinetic Monte CarloMicrostructural evolution during irradiation
Dislocation DynamicsDislocation behavior during deformation
Detailed analysis of microstructure
Point defect production
Cu atoms
Vacancies
Dislocationloop
Dislocation
Radiation damage
Molecular Dynamics
Molecular Dynamics
Stres
s (MP
a)
Strain (%)
~10-11sec~10-8m
~109sec~10-7m
~100sec~10-4m
Dislocation DynamicsPrediction of mechanical property ~100m
Unirradiated
Irradiated
Interaction between dislocation and damage
19
NanoNano--structural Characterizationstructural Characterization
3-Dimensional Atom ProbePositron Annihilation
(Coincidence Doppler Broadening)
1.4
1.2
1.0
0.8
0.6
Rat
io to
Fe
50403020100PL (x10-3 m0c)
Unirrad. As-irrad. 500°C
規格
化され
た強度
電子の運動量
未照射材照射材
熱時効材
Cu-enriched clusters formed by neutron irradiation
~40 nm
~300
nmLEAP
(Local Electrode Atom Probe)
Norm
alize
d cou
nts of
gamm
a ray
s
Electron momentum
Irradiated unirradiated
thermallyaged
20
New Embrittlement Correlation for JEAC 4201New Embrittlement Correlation for JEAC 4201
MDMD CT ⋅=∆ 18ξ
( ) ( )22MDSC TTT ∆+∆=∆
( ) ( ) ( ) SCNiSCmatCufSC CthCgCCfVT ⋅+⋅⋅⋅=⋅=∆ φξξξ 0
161717 ,
( )( ) ( )( )2089214 1 NiCu
availCuMDCu
matCu
SC CDCCDCt
C ⋅+⋅⋅⋅+⋅+⋅+⋅=∂
∂ ξξξξξ
( )t
CCFt
C SCNit
MD
∂∂−⋅⋅+⋅⋅=
∂∂ φξξξ 2
762
5
SCSC
enhSc
SC
matCu Cv
tCv
tC ⋅′−
∂∂⋅−=
∂∂
21
ηφη ⋅+=+= thermalCu
irradCu
thermalCuCu DDDD
( )t
CCFt
C SCNit
MD
∂∂−⋅⋅+⋅⋅=
∂∂ φξξξ 2
762
5
21
プラント補正なし
プラント補正あり
-20
0
20
40
60
80
100
120
140
-20 0 20 40 60 80 100 120 140
監視試験測定値(℃)
予測値
(℃)
補正なし
補正あり
1:1
-2σ
+2σ
0.15.4CRIEPI adj0.79.4CRIEPI2.311.7E900-022.810.4EWO-1.915.4RG1.99r2-1.311.9JEAC4201
Mean ErrorStd. Dev.Method
Pred
iction
(oC)
Measured value (oC)
w/o adjustmentw adjustment
∆T
φtOffset
∆T
φtOffset
Plant specific adjustment
Comparison of DBTT shift betweenComparison of DBTT shift betweenthe measured value and the predictionthe measured value and the prediction
22
RVH nozzle environmental shielding weld (seal welding over cracking)
RVH nozzle penetration repair technique
Overlay weldOverlay weld
The structure and application of Inconel 690 repair weld have been approved by the verification committee, RTTW committee and CRT
committee.
Cracking
Applying corrosion resistant Inconel 690 overlay weld directly over through-wall cracking
Repair welding machine
Repair weld applied to through-wall cracking in J-groove weld
Through-wall cracking
Repair Welding Technique Development; MHIRepair Welding Technique Development; MHI
weld
Weld device
三菱重工原子力技術資料:クラスB
All Rights Reserved, Copyright (C), MITSUBISHI HEAVY INDUSTRIES,LTD. 23
History of Troubles and Preventive Maintenance of RVHHistory of Troubles and Preventive Maintenance of RVH
▼
1980 1990 2000
Trouble
R/V<head penetration nozzle><BMI nozzle>
Present
S/G<Tube>
SCC of tubes of S/G in Japan (MA600)
SCC of tubes of S/G in Japan (TT600)
SCC of nozzle of pressurizer at Tsuruga unit-2 (2003)
SCC of R/V head nozzle at Bugey unit-3 in France(1991) ▼
SCC of R/V outlet nozzle at V.C.Summer in the U.S. (2000) ▼
SCC of R/V head nozzle at Oconee unit-1 in the U.S. (2000) ▼ SCC of BMI nozzle at South Texas Project unit-1 in the U.S. ▼ (2003)
ECT of R/V head penetration nozzle
Replacement of R/V head
R/V,Pressurizer ,S/G<Safe-end welds of nozzle>
Preventive Maintenance
Reduction of R/V head top temperature(Takahama3.4,Ohi3.4)
Intelligent ECT of tube of S/G (TT600)Replacement of S/G(MA600→TT690)
Shot-peening of tubes of S/G (TT600)
WJP / ECT of BMI nozzle (base metal)
WJP of R/V inlet/outlet nozzleShot-peening of S/G inlet/outlet nozzleLaser stress improvement of Pzr nozzle
WJP of BMI nozzle(weld metal)
UT (angle beam,longitudinal wave) of safe-end welds of nozzle (R/V,Pressurizer,S/G)
SCC of nozzle of R/V head nozzleat Ohi-3 (2004) ▼
SCC of BMI nozzle at Takahama-1(2002) ▼
Replacement of R/V head(Takahama3.4,Ohi3.4)
24
Reactor Vessel Head Nozzle MaintenanceReactor Vessel Head Nozzle Maintenance200520001995 2010 2015
ECT
▼Bugey 3Leak(1991)(France)
VHR
T-Cold VHR
▼Davis-Besse Leak(2002)
▼Ohi3 Leak(2004)
Older PlantsMihama 1,2,3Takahama 1,2Ohi 1,2
New PlantsTakahama 3,4Ohi 3,4
Preventive maintenance (T-Cold) has been conducted at new plants with a lower possibility of PWSCC in order to mitigate PWSCC susceptibility.
ECT had been conducted at old plants with a relatively high possibility of PWSCC.
VH had been replace at old plants with a relatively high possibility of PWSCC.
Replacement of VH is also planned for new plants.
PlugPlug hole Increased plug hole diameter
Change of nozzle Base & J-Weld material. Alloy 600 Alloy 690(Improved corrosion resistance)
25
1. Purpose・Mitigation of SCC for pipes orcylindrical equipments
2. Effect・Residual Stress Improvementl for weld joints and HAZ onthe inner surface
3. Experiences・BWR Plants in Japan
HAZ : Heat Affected Zone
Induction Heating Stress Improvement((((IHSI))))
PipePipe
CoolantCoolantCoolantCoolant
IH coil
All Rights Reserved Copyright © 2007, Hitachi-GE Nuclear Energy, Ltd.
26
Controller
Laser systemOptical fiber
CRD stub tube
Remote handlingsystem
Shroud
Preventive Maintenance Technology DevelopmentPreventive Maintenance Technology Development
�Development of a laser peeningsystem for core shroud.�Application for Japanese nuclear reactors (BWR) since 1999.�Development and application of a fiber-delivered system since 2002.�Experiences in BWRs: 8 plants.
CRD Stub Tubes> 4 plantsCore Shroud>5 Plants
�PWR Applications since 2004:2 plants.
Copyright © 2006 Toshiba Corporation. All rights reserved.
Fiber-delivered Laser Peening SystemApplication for CRD Stub Tubes ((((BWR))))
27
Recent activity and LP System architecture Recent activity and LP System architecture
Road Map: Examples of R&D and Good Practices Road Map: Examples of R&D and Good Practices
28
1F-1~~~~5: Early
SCC of type 304 piping, oversea & domestic NPP
SCC of type 316L▼▼▼▼
at PLR Piping, H-3 NPP
▼▼▼▼
▼▼▼▼UT indicationnozzle, oversea NPP
SCC of type 304Lshroud, oversea NPP
SCC of type 316L piping, domestic NPP
‘70 ‘80 ‘90 ‘00Major Events
Materials Improvements
Stress Improvements
Environment Improvements
Replacement Repair
Coun
term
easu
res
Major R&D
Type 304 NP 1F-6, 2F-1After NP 2F-2
Type 304LType 316(LC)
Induction Heating Stress Improvement, Heat Sink Welding, Corrosion Resistance CladdingNP 1F-6, 2F-1 Replace: 1F-1~~~~5
All plants
Start-up deaeration Operation
Hydrogen injectionNoble metal chemical addition
1F-1~~~~6、、、、2F-3 etc.
2F-3
Except main piping Main piping To expand whole type 316L
1F-1~~~~5 (Type 304+Stress improve)Development of low carbon SS
Development of Countermeasures to SCC
Development of Hydrogen injection
1F-1~~~~5
PMT, WIM(JAPEIC/JNES projects)
Experiences and Countermeasures of SCC in PLR PipingExperiences and Countermeasures of SCC in PLR Piping
Proprietary Information
Cooperation with International OrganizationsCooperation with International Organizations• IAEA
Ageing Management Guideline (for aged NPP)• OECD/NEA
SCAP SCC and Cable Ageing ProjectIAGE Metal-Concrete-Earthquake Resistance-HF Steering GroupOPDE OECD Pipe failure Data Exchange Project
• USANRC PINC ProjectASME Sec.XI Code CommitteeIEEE Cable Environmental Qualification Test
• IECRadiation Effect Interpretation (Judgment) Criteria
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Davis-Besse Reactor Vessel Head Degradation
Project Organization
Steering Committee
U.S. Nuclear Regulatory Commission (USNRC) proposed international cooperative research Project for the IIIInspection of Nickel-alloy Components (PINC). And Five country eight organizations
are participating in PINC to address common problem.
TG-AtlasDevelop an electronic Atlas (database) of NDE and metallography information TG-NDERound Robin of NDE techniques on PWSCC and simulated cracks
PINC Project
(2004~2008)
30
Round Robin Test in TG-NDE
Performance to detect PWSCC will be clarified and the results will be reflected to regulatory guidelines andprocess qualifications by NDI test of CRDM, BMI, Safe-end dissimilar metal welds.
Sample of CRDM TPs Sample of BMI TPs Sample of DMW TPs
PINC Project
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OECD/NEA OECD/NEA SCAP ProjectSCAP Project **
• The main objectives of SCAP are to:– Establish a complete database with regard to major ageing phenomena for SCC and degradation of cable insulation through collective efforts by OECD/NEA members– Establish a knowledge-base by compiling and evaluating collected data and information systematically, with regard to major ageing phenomena for SCC and degradation of cable insulation– Perform an assessment of the data and identify the basis for commendable practices which would help regulators and operators to enhance ageing management
SCAP: Stress Corrosion Cracking and Cable Ageing Project
*This project is being financed through Japanese voluntary contribution 32
(Members)・Belgium・Canada・Czech Republic・Finland・France・Germany・Japan・Korea・Mexico・Norway・Slovak Republic・Spain・Sweden・U.S
Management Board
Cable WGSCC WG
(Observers) IAEA, EC
MB Chair Prof.Sekimura
(Japan)
SCC Chair Mrs. Gott (Sweden)
SCAP Consultant Mr. Shultz (Germany)
Cable Chair Mr. Koshy (U.S)
Clearing House
ERIN(U.S)
Clearing HouseOECD Halden
Reactor ProjectIFE(Norway)
Management of the SCAPManagement of the SCAP
Technical Secretariat 33