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PLiM Symposium in Shanghai
Structural Integrity Evaluation of Cast Austenitic Stainless Steel
Reactor Coolant Piping for Continued Operation of Nuclear Power Plants
PLiM Symposium in Shanghai
Structural Integrity Evaluation of Cast Austenitic Stainless Steel
Reactor Coolant Piping for Continued Operation of Nuclear Power Plants
2007년년년년 10월월월월 18일일일일
YOUNG JONG KIMGNEC
2007년년년년 10월월월월 18일일일일
YOUNG JONG KIMGNEC
11
INTRODUCTIONIIII
SUSCEPABILITY EVALUATIONIIIIIIII
CONCLUSIONIVIVIVIV
Contents
FLAW TOLERANCE EVALUATIONIIIIIIIIIIII
22
I . INTRODUCTIONI . I . INTRODUCTION
33
I . INTRODUCTIONI . I . INTRODUCTION
• NPP Life Extension - 40 years � 60 years, 48 NPP in the USA; - 30/40 years � 40/50 years in some European Countries
• In Korea, - 20 nuclear power plants (16 PWRs and 4 CANDUs) in operation. - Licensed design lifetime: Kori Unit 1(PWR) & 4 CANDUs: 30 yearsOthers: 40 years
• NPP life extension in Korea- 10 year extension is now under review for Kori Unit 1:- the first NPP in Korea, - operated since 29 April 1978.
44
Design ConditionsDesign Pressure: 2485 psigOperating Pressure: 2235 psigDesign Temp: 650°°°° F
Reactor Coolant Piping- two hot legs, - two cold legs and - two crossover legs
Reactor Coolant Piping of Kori Unit 1
55
Cast austenitic stainless steel thermal aging issuesCast austenitic stainless steel thermal aging issuesCast austenitic stainless steel thermal aging issuesCast austenitic stainless steel thermal aging issuesCast austenitic stainless steel thermal aging issuesCast austenitic stainless steel thermal aging issuesCast austenitic stainless steel thermal aging issuesCast austenitic stainless steel thermal aging issues
fatigue crack growth Evaluation, flaw tolerance evaluationfatigue crack growth Evaluation, flaw tolerance evaluationfatigue crack growth Evaluation, flaw tolerance evaluationfatigue crack growth Evaluation, flaw tolerance evaluation
susceptibility susceptibility susceptibility susceptibility evaluationevaluationevaluationevaluation for thermal aging for thermal aging for thermal aging for thermal aging embrittlementembrittlementembrittlementembrittlement
reduction of fracture toughnessreduction of fracture toughnessreduction of fracture toughnessreduction of fracture toughness
CASS material CASS material CASS material CASS material ---- RCPB componentsRCPB componentsRCPB componentsRCPB componentsCASS material CASS material CASS material CASS material CASS material CASS material CASS material CASS material -------- RCPB componentsRCPB componentsRCPB componentsRCPB componentsRCPB componentsRCPB componentsRCPB componentsRCPB components
reactor coolant pipingreactor coolant pipingreactor coolant pipingreactor coolant piping
CASS( 14% to 20% ferrite)CASS( 14% to 20% ferrite)�� thermal aging thermal aging embrittlementembrittlement
to resolve the thermal aging issuesto resolve the thermal aging issuesto resolve the thermal aging issuesto resolve the thermal aging issues
fitting valve bodies, and reactor coolant pump casingfitting valve bodies, and reactor coolant pump casingfitting valve bodies, and reactor coolant pump casingfitting valve bodies, and reactor coolant pump casing
66
II. SUSCEPTIBILITY EVALUATIONII. II. SUSCEPTIBILITY EVALUATION
77
II. II. SUSCEPABILITY EVALUATION
Aubrey’s equationThe ferrite contents were calculated using chemical compositions in CMTR and Aubrey’s equation
the potential susceptibility was derived by comparing with the screening criteria of USNRC
Screening criterionfor a straight pipe < 20 % of ferrite contentfor a fitting and an elbow < 14 % of ferrite content
88
II. II. SUSCEPABILITY EVALUATION
18Static27.5-RC-B-11036 (35°°°°elbow)17Centrifugal27.5-RC-A-11036 (straight)16Static27.5-RC-A-1103 (35°°°°elbow)15Centrifugal27.5-RC-A-1103 (straight)
Coldleg
14Static31-RC-B-1105 (40°°°°fitting)13Static31-RC-B-1105 (90°°°°elbow)12Static31-RC-B-1105(90°°°°elbow with splitter)11Centrifugal31-RC-B-1105 (straight)10Centrifugal31-RC-B-1105 (straight)9Static31-RC-A-1102 (40°°°°fitting)8Static31-RC-A-1102 (90°°°°elbow)7Static31-RC-A-1102(90°°°°elbow with splitter)6Centrifugal31-RC-A-1102 (straight)5Centrifugal31-RC-A-1102 (straight)
Cross-over leg
4Static29-RC-B-1104 (50°°°°fitting)3Centrifugal29-RC-B-1104 (straight)2Static29-RC-A-1101 (50°°°°fitting)1Centrifugal29-RC-A-1101 (straight)
Hot leg
No.Casting methodSubparts (OD-system-loop-subcomponent no.)Piping
Specifications for Subparts of Reactor Coolant Piping of Kori Unit 1
99Non-acceptable< 1416.7218Acceptable< 1413.15
35°°°° elbows16
Acceptable< 2019.1717Acceptable< 2017.81
Straight pipesColdleg
15Non-acceptable< 1414.5814Non-acceptable< 1414.58
40°°°° fittings9
Non-acceptable< 1414.8113Non- acceptable< 1414.16
90°°°° elbows8
Acceptable< 1412.9912Non- acceptable< 1416.3490°°°° elbows
with splitter7
Acceptable< 2017.4211Acceptable< 2017.42
Straight pipe 210
Acceptable< 2014.166Acceptable< 2014.16
Straight pipe 1
Cross-over leg
5Acceptable< 1410.824
Non- acceptable< 1414.5850°°°° fittings
2Non- acceptable< 2021.093Acceptable< 2012.58
Straight pipesHot leg
1
SusceptabilityScreeningCriteria (Vol.%)
Ferrite Contents (Vol.%)
SubpartsNo.
Susceptibility Evaluation Results
II. II. SUSCEPTIBILITY EVALUATION
1 straight pipe and7 fittings/elbows potentially susceptible to thermal aging embrittlement
1010
III. FLAW TOLERANCE EVALUATIONIII. III. FLAW TOLERANCE EVALUATION
1111
III. III. FLAW TOLERANCE EVALUATION
Flaw Tolerance Evaluation Procedureto ensure the structural integrity of CASS reactor coolant piping subparts
NUREG-1801Two evaluation methods recommended - to demonstrate the integrity through enhanced volumetric examination- to perform plant specific and component specific flaw tolerance evaluation considering material property changes due to thermal aging embrittlement .
flaw tolerance evaluation proceduresand acceptance criteria for CASS piping - ASME Code Section XI , IWB-3640.
1212
Flow Chart for Flaw Tolerance Evaluation Procedure
StartStartStartStart
Crack ConfigurationCrack ConfigurationCrack ConfigurationCrack Configuration
Axial Surface CrackAxial Surface CrackAxial Surface CrackAxial Surface Crack Circ. Surface CrackCirc. Surface CrackCirc. Surface CrackCirc. Surface Crack
Stress Distribution CalculationStress Distribution CalculationStress Distribution CalculationStress Distribution Calculation
Stress Intensity Factor (KStress Intensity Factor (KStress Intensity Factor (KStress Intensity Factor (KIIII) ) ) )
Calc.Calc.Calc.Calc.
Fatigue Crack Growth Fatigue Crack Growth Fatigue Crack Growth Fatigue Crack Growth EvaluationEvaluationEvaluationEvaluation
Crack GrowthCrack GrowthCrack GrowthCrack Growtha = a + a = a + a = a + a = a + dadadadac = c + dcc = c + dcc = c + dcc = c + dc
Crack DepthCrack DepthCrack DepthCrack Depth> > > > AccepAccepAccepAccep. . . . CriteriaCriteriaCriteriaCriteria
EndEndEndEnd
Stress AnalysisStress AnalysisStress AnalysisStress AnalysisResultResultResultResult
YesYesYesYes
NoNoNoNo
Crack Evaluation Crack Evaluation Crack Evaluation Crack Evaluation At end of lifetimeAt end of lifetimeAt end of lifetimeAt end of lifetime
III. III. FLAW TOLERANCE EVALUATION
1313
Hot Leg Stress Analysis ResultsPiping Load Stress in Elbow Region
Unit: Pa
III. III. FLAW TOLERANCE EVALUATION
1414
Crossover Leg Stress Analysis ResultsMaximum Pressure Stress
Axial Stress Hoop Stress Unit: Pa
III. III. FLAW TOLERANCE EVALUATION
1515
Cold Leg Stress Analysis ResultsMaximum Pressure Stress
Axial Stress Hoop Stress Unit: Pa
III. III. FLAW TOLERANCE EVALUATION
1616
Fatigue Crack Growth Equation
( )( )45.0max
11 1101465.5da/dN RK −×= −
a = Crack depth (in)N = Number of cyclesR = Kmax/KminKmax ,Kmin= Maximum and minimum stress intensity factor(ksi-in1/2)
- EPRI(1000976; 2001) Fatigue Crack Growth Equation- PWR primary water environment test(320°C)- Upper Bound Curve for all the crack growth data
III. III. FLAW TOLERANCE EVALUATION
1717
o ASME XI, Appendix L, L-3200(Table L-3210-1)
Initial Crack Assumption
* Aspect Ratio(6:1)
III. III. FLAW TOLERANCE EVALUATION
1818
III. III. FLAW TOLERANCE EVALUATION
Hot Leg Fatigue Crack Growth Evaluation (axial)Crack depth at end of life=0.42 in=10.67 mm
mMPainksiK I 1.175.15life) of (end ==
1919
Hot Leg Fatigue Crack Growth Evaluation (circumferential)Crack depth at end of life=1.12 in=28.45 mm
III. III. FLAW TOLERANCE EVALUATION
mMPainksiK I 3.274.28life) of (end ==
2020
Final Axial Crack Depth for CASS Piping Subparts
14.8110.1612.698.712268.5835°°°° elbowColdleg
14.6711.1811.78.915476.290°°°° elbow
with splitter
14.6711.1811.78.915476.290°°°° elbow14.010.6711.78.915476.240°°°° fitting
Cross-overleg
14.4410.2712.368.788471.12Straight pipe At the
maximum hoop stress
generation location
in each subpart
15.010.6712.368.788471.1250°°°° fittingHot leg
Depth ratio (%)
depth(mm)
Depth ratio (%)
Depth (mm)
Crack locationcalculated
Final crackInitial crack Pipe Thick-ness
Subparts
III. III. FLAW TOLERANCE EVALUATION
2121
III. III. FLAW TOLERANCE EVALUATION
Failure mode Evaluation- ASME B&PV Code, Sec.XI, App.C, Article C-4000- failure modes of almost all subparts : FPF- fully-plastic fracture (FPF) � ductile fracture (DF), because tensile property may increase, while fracture toughness may decrease due to thermal aging embrittlement.
2222
Failure Mode Evaluation Results for Axial Cracks
DF (EPFM analysis)0.27216434.6135°°°° elbowColdleg
FPF (limit load analysis)0.19618720.8490°°°° elbow with splitter
FPF (limit load analysis)0.19618720.8390°°°° elbow
FPF (limit load analysis)0.19218720.5140°°°° fittingCross-overleg
FPF (limit load analysis)0.175203.520.29StraightPipe
FPF (limit load analysis)0.177203.520.5550°°°° fittingHot leg
RemarksSC(=K’r/S’r)
Min. fracture toughness
KIc(MPa m0.5)
Max. SIF at final crack size
KI-max(MPa m0.5 )Subparts
Note) FPF if SC<0.2; DF if 0.2≤≤≤≤SC<1.8
III. III. FLAW TOLERANCE EVALUATION
2323
Flaw Tolerance Evaluation Results for Axial Cracksthe results of flaw tolerance evaluation for axial cracks at the end of continued operationstructural integrity of CASS RC piping be maintained over 40 years
0.440.14835°°°° elbowCold leg
0.70.14790°°°° elbow with splitter
0.70.14790°°°° elbow0.70.14040°°°° fitting
Cross-over leg
0.70.144Straight pipe Structural integrity
will be maintained over the continued operation period.
0.70.15050°°°° fittingHot leg
RemarksAllowable
crack depth ratios
Evaluated crack depth
ratiosSubparts
III. III. FLAW TOLERANCE EVALUATION
2424
IV. CONCLUSIONIV. IV. CONCLUSION
2525
CONCLUSIONCONCLUSION
integrity evaluation of CASS RC piping of Kori Unit 1considering the change of material properties due to thermal aging embrittlement.
predicted fatigue crack growths- not significant for all CASS RC piping.
final crack sizes (40 years) - satisfied in accordance with the ASME Section XI acceptance criteria.
structural integrity of CASS reactor coolant piping- maintained over 40 years.
Thank you very much.Thank you very much.