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Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR H. S. Kushwaha 4 th AERB-NRC Technical Discussion Meeting Aug. 30 – Sept. 3, 2004 Use of PRA in LBB analysis
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Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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Page 1: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

Probabilistic Leak Before Break of 540 MWTarapur :3/4 PHWR

H. S. Kushwaha

4th AERB-NRC Technical Discussion Meeting

Aug. 30 – Sept. 3, 2004

Use of PRA in LBB analysis

Page 2: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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Basic Steps in LBB

• Level 1 : Stringent design criteria

• Level 2 : Fatigue crack growth analysis

• Level 3 : Instability analysis

Page 3: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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Level 1 Safety Analysis in LBB

• Design done with a well-defined factor ofsafety using ASME Sec.III.

• Does not consider the presence of flaw.

• Sufficiently tough material is chosen forpiping components.

• Minimize number of weld joints

• 100% radiography/ultrasonic Examination.

Page 4: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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Level 2 Safety Analysis in LBB

crack

• Postulate part-through flaw that escape NDT

• Perform fatigue crack growth study of the flawover the entire life period of the reactor.

• Show that the final flaw size is less than 75% ofwall thickness

Page 5: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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Level 3 Safety Analysis in LBB

• Identify the critical location: Section with less favorablecombination of stress and material properties.

• Postulate a through wall crack (LSC). that will lead to detectable leakage.• Perform stability assessment and calculate the critical load

(Mc) of the piping component with postulated LSC.• Calculate critical crack size (ac) with the

maximum credible load on piping component.• Demonstrate : Mc/(MNOC+SSE) = 1 and ac/LSC = 1 for ABS

load earthquake combination

crack

Page 6: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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Application of LBB requires

• Knowledge of DBA loads• Geometry of the pipes• Material properties of pipe• Leakage size crack

• Some of these show variability• Requires Application of Probabilistic Fracture

MechanicsProbability that LSC is not critical under NOC+SSE

Page 7: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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Salient Features of the Analysis

• Critical locations• Welds in straight pipe• Elbows, Crack at Extrados

� Steam Generator Inlet (SGI)� Steam Generator Outlet (SGO)� Pump Discharge Line (PDL)

• Critical Load: NOC + SSE

Page 8: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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PHWR Reactor

SGI SGO

PDL

Page 9: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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PHWR Reactor

Page 10: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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Reliability analysis

• Data for uncertainty quantification• Material Properties

� Fracture Toughness, Fracture Resistance curve� Yield Stress, Ultimate Stress, Stress-Strain Curve

• Leakage size crack• Frequency of occurrence of SSE load

• Mechanism of failure• Net Section Collapse• J-Tearing: Crack Driving Force• R6: Failure Assessment Diagram

Page 11: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

11

Net Section Collapse (NSC)

Page 12: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

12

R6 Method

Page 13: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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J-Tearing Method

fail Appliedload

Materialresistancecurve

Page 14: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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BARC: Comprehensive ComponentIntegrity Test Program

• Fracture tests : 45 (CS) + 14 (SS)• Fatigue tests : 28 (CS) + 19 (SS)• Cyclic tearing tests : 24• Tests carried out on straight pipes and elbows at

room temperature• Sizes : 8” – 16” Nominal Bore (NB)• Tests also carried out on 100 CT specimens at RT,

200-300°C• Period of tests : 1999 - 2003

Page 15: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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Through wall circumferential crackBARC Fracture Tests: Crack

Configurations in Piping Components

crack

crack weld

crack

crack

Through wall circumferential crack Part through circumferential crack

Through wall circumferential crack in weld

Page 16: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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BARC Fracture Tests: CrackConfigurations in Elbows

Crack at extrados Crack at Crown

Page 17: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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Fracture Test on Through WallCircumferentially Cracked Pipe

Set-up Crack growthpattern

Page 18: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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Set-upCrack growth

pattern

Fracture test on surface crackedpipe

Page 19: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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Crack growthPattern

Crack opening

Set-upFracture Tests on ElbowsFracture Tests on Elbows

Page 20: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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0 40 80 120 1600

35

70

105

140

Expt. FEM

Crack initiation

Load

(kN

)

Displacement (mm)

Comparison of Load Deflection Curve

Page 21: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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Net Section Load andExperiments

( )Circumferential Crack Angle /θ π

00.20.40.60.8

11.2

0 0.1 0.2 0.3 0.4 0.5 0.6

theoretical k = 2theoretical k = 2.48" experimental16" experimental

( )24 cos / 2 0.5sin( )l fM R tσ θ θ= −� �� � ( )u yf k

σ σσ

+=

Page 22: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

22

BARC Fracture Tests

• Maximum load observed in pipes up to 8” NB size isnearly same as that based on NSC (using flow stress)

• Maximum load observed in pipes = 12” NB size is lessthan that based on NSC, hence J-Tearing governs thefailure.

• In pipes = 12” NB there is large margin between crackinitiation and unstable fracture.

• In all cases maximum load observed is greater than thatbased on NSC (using σy)

• The tests revealed that load carrying capacity under cyclicloads is less. It is compensated by compliance effects ofpiping system due to which moment redistribution occurs.

Page 23: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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Reliability Analysis

• Estimation method• Fast Probability Integration

� FORM� SORM

• Simulation� Classical Monte Carlo Method (CMC)� Monte Carlo with

– Importance Sampling (IS)– Adaptive Importance Sampling (AIS)– Conditional Expectation (CE)– Adaptive Stratified-Importance Sampling (VEGAS numerical

integration algorithm)

Page 24: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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Description of Pipes

LSC has Guassian distribution with cov = 10%

85.624234.035211PDL

40456432.450280SGO

33939134.640234SGI

SSE LoadkN-m

NOC LoadkN-m

MeanLSCDeg.

Thick.(mm)

MeanRadius(mm)

PipeLine

Page 25: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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Probabilistic LBB Qualification

327.624285.6PDL

968564404SGO

730391339SGI

DBA(NOC + SSE)Moment

NOCMoment

SSEMoment

Moments in kN-m

Uncertainty in SSE Moment only (Lognormal Distribution)

Page 26: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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Stochastic Treatment of Load

• The distribution of induced moment is consideredas lognormal

• The SSE value as computed by piping analysis isconsidered as Mean Centered

• The SSE moment corresponds to PGA of 0.2g• The variability [aleatory and epistemic] arises in

• Piping Dynamic Response (PDR)• Building Dynamic Response (BDR)

Page 27: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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Piping Dynamic ResponseVariability

• Floor Spectra• Spectral Shape – Peak Broadening• Artificial Time History – Enveloping the Design Ground spectra

• Modeling Factors in Piping analysis• Boundary Conditions, Geometry/Layout, Modeling.

• Damping Factors• Model Combination• Earthquake Component Combinations

• Vertical and Horizontal (North and South)

0.31 0.27PDR PDRaleatory epistmic δ δ= =

Page 28: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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Building Structural ResponseVariability

• Ground Spectrum Shape• Damping of RCC• Modeling: Building, Floors etc.• Soil Structure Interaction

0.25 0.18BDR BDRaleatory epistmic δ δ= =

0.40 0.32aleatory epistmic δ δ= =Combining

Lognormal distribution for seismic load

Page 29: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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Material PropertiesC-Mn Steel (SA333-Gr6)

4

var

240.0 282.24 113.148449.0 113.148 504.0

1.948 0.607 0.44.898 0.4 0.406

412.0 2.716 10 43.93587.330.433

y

u

ic

RandomVector MeanVeactor Co ianceMatrix

n

JCm

σσα

� � � � � �� � � � � �

� �

−� � � � � �� � � � � �− � �

× −� � � � � � � �

4

7 6.2343.937 3.105 10 8.563

6.23 8.563 0.012

� �−� �− ×� �� �−� �

σu and σy are in MPa,JIC and C are in kJ/m2

•Stress-strain curve is represented by Ramberg-Osgood fit (α, n)•J-R curve is represented by power fit equation (C, m)JR(∆a) = C(∆a)m

All are lognormally distributed

Page 30: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

30

05

10152025

0.365

0.438

0.511

0.584

0.657

0.730

0.803

0.876

0.949

1.020

Load MN-m

Rel

iabi

lity

Inde

x

FORMISAIS

NSC Results: SGI – ConstantDBA Load

Page 31: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

31

NSC Results: SGO -ConstantDBA Load

0

5

10

15

20

25

0.484

0.581

0.678

0.774

0.871

0.968

1.060

1.160

1.260

1.360

Load MN-m

Rel

iabi

lity

Inde

x

FORMISAIS

Page 32: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

32

NSC Results: PDL -ConstantDBA Load

05

1015202530

0.164

0.197

0.229

0.000

0.000

0.328

0.360

0.393

0.426

0.459

Load MN-m

Rel

iabi

lity

Inde

x

FORMISAIS

Page 33: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

33

2.00

2.50

3.00

3.50

4.00

4.50

5.00

5.50

6.00

6.50

0.365 0.438 0.511 0.584 0.657 0.73 0.803 0.876 0.949 1.02

Bending Moment (MN-m)

β

FORMCMCISVEGASSORMAISCE

R6 Results: SGI -Constant DBALoad

Results for high reliability index > 4could not be obtained using CMC becauseof computational limitations

Page 34: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

34

R6 Results: SGO -Constant DBALoad

2.00

2.50

3.00

3.50

4.00

4.50

5.00

5.50

6.00

6.50

7.00

0.484 0.581 0.678 0.774 0.871 0.968 1.06 1.16 1.26 1.36

Bending Moment (MN-m)

β

FORMCMCISVEGASSORMAISCE

Results for high reliability index > 4could not be obtained using CMC becauseof computational limitations

Page 35: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

35

R6 Results: PDL -Constant DBALoad

2.00

3.00

4.00

5.00

6.00

7.00

8.00

0.164 0.197 0.229 0.262 0.295 0.328 0.36 0.393 0.426 0.459

Bending Moment (MN-m)

β

FORMISVEGASSORMAISCE

Page 36: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

36

Effect of Variability of FractureToughness on Reliability Index

0.002.00

4.006.00

8.0010.00

12.0014.00

16.000.

1

0.13

0.16

0.19

0.22

0.25

0.28

0.31

0.34

0.37 0.4

Coefficient of variation of weld fracture toughness

Rel

iabi

lity

Inde

x

SGI Pipe

Sitewelding

Shop floorwelding

Page 37: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

37

Reliability Index@DBA: Comparing forDifferent Pipes-constant Applied Load

02468

1012141618

ββββ

SGISGOPDL

SGI 11.9 3.8 8.3 9.8SGO 15.7 4.3 9.3 10.9PDL 17.9 5.1 10.3 11.9

NSC R6 init. R6 rupture J-T

Page 38: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

38

SGI NSC

1.E-07

1.E-06

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

0.E+00 2.E+06 4.E+06 6.E+06 8.E+06 1.E+07Moment N-m

Pf

5%50%95%

Fragility Analysis-SGI: NSC-Stochastic Load

Page 39: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

39

SGO NSC

1.E-091.E-081.E-071.E-061.E-051.E-041.E-031.E-021.E-01

1.E+00

0.0E+00 2.0E+06 4.0E+06 6.0E+06 8.0E+06 1.0E+07 1.2E+07 1.4E+07

Moment N-m

Pf

5%50%95%

Fragility Analysis-SGO: NSC -Stochastic Load

Page 40: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

40

PDL NSC

1.E-101.E-091.E-081.E-071.E-061.E-051.E-041.E-031.E-021.E-01

1.E+00

0.E+00 1.E+06 2.E+06 3.E+06 4.E+06 5.E+06 6.E+06 7.E+06Moment N-m

Pf

5%50%95%

Fragility Analysis-PDL: NSC -Stochastic Load

Page 41: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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SGI R6 Initiation

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

0.E+00 2.E+06 4.E+06 6.E+06 8.E+06Moment N-m

Pf

5%50%95%

Fragility Analysis-SGI: R6(INITIATION) - Stochastic Load

Page 42: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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SGO R6 Initiation

1.E-06

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

0.E+00 2.E+06 4.E+06 6.E+06 8.E+06Moment N-m

Pf

5%50%95%

Fragility Analysis-SGO: R6(INITIATION) - Stochastic Load

Page 43: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

43

PDL R6 Initiation

1.E-07

1.E-06

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

0.E+00 1.E+06 2.E+06 3.E+06 4.E+06 5.E+06Moment N-m

Pf

5%50%95%

Fragility Analysis-PDL: R6(INITIATION) - Stochastic Load

Page 44: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

44

SGI R6 Max

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

0.E+00 2.E+06 4.E+06 6.E+06 8.E+06Moment N-m

Pf

5%50%95%

Fragility Analysis-SGI: R6 (UNSTABLECRACK GROWTH) - Stochastic Load

Page 45: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

45

SGO R6 Max

1.E-06

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

0.0E+00 2.0E+06 4.0E+06 6.0E+06 8.0E+06 1.0E+07 1.2E+07 1.4E+07

Moment N-m

Pf

5%50%95%

Fragility Analysis-SGO: R6 (UNSTABLECRACK GROWTH) - Stochastic Load

Page 46: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

46

PDL R6 Max

1.E-07

1.E-06

1.E-05

1.E-04

1.E-03

1.E-02

1.E-01

1.E+00

0.0E+00 1.0E+06 2.0E+06 3.0E+06 4.0E+06 5.0E+06 6.0E+06

Moment N-m

Pf

5%50%95%

Fragility Analysis-PDL: R6 (UNSTABLECRACK GROWTH) - Stochastic Load

Page 47: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

47

SGI J-T

1.E-081.E-07

1.E-061.E-05

1.E-041.E-03

1.E-021.E-01

1.E+00

0.0E+00 2.0E+06 4.0E+06 6.0E+06 8.0E+06 1.0E+07

Moment N-m

Pf

5%50%95%

Fragility Analysis-SGI: J-TEARINGMETHOD - Stochastic Load

Page 48: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

48

SGO J-T

1.E-101.E-091.E-081.E-071.E-061.E-051.E-041.E-031.E-021.E-01

1.E+00

0.0E+00 5.0E+06 1.0E+07 1.5E+07 2.0E+07

Moment N-m

Pf

5%50%95%

Fragility Analysis-SGO: J-TEARINGMETHOD - Stochastic Load

Page 49: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

49

PDL J-T

1.E-111.E-101.E-091.E-081.E-071.E-061.E-051.E-041.E-031.E-021.E-01

1.E+00

0.0E+00 1.0E+06 2.0E+06 3.0E+06 4.0E+06 5.0E+06 6.0E+06 7.0E+06 8.0E+06

Moment N-m

Pf

5%50%95%

Fragility Analysis-PDL: J-TEARINGMETHOD - Stochastic Load

Page 50: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

50

0

1

2

3

4

5R

elia

bilit

y In

dex

SGI 3.4 2.2 3.1 3.6SGO 4.2 2.8 3.8 4.3PDL 4.6 3.3 4.2 4.8

NSC R6 init. R6 rupture J-T

Reliability Index@DBA: Comparing forDifferent Pipes-Stochastic Applied Load

Page 51: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

51

Calculation of Margin on Loadfor LBB

0.0001

0.001

0.01

0.1

1

0.E+00 1.E+06 2.E+06 3.E+06 4.E+06 5.E+06 6.E+06

Bending Moment

Pf

50 % confidence load

95 % confidence load

0.05

M1M2

LoadSSENOC2or 1

+MM

ProbabilisticLBB Margin

Page 52: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

52

LBB Margins at Constant Load(Margin Required :ABS Load Combination=1

11.14.139.293.829.293.4210.84.15PDL

9.063.477.623.204.742.989.343.63SGO

5.642.605.652.403.422.246.602.65SGI

J-TR6 ruptureR6 init.NSC

Deterministic

Probabilistic

Margins calculated at 95% confidence moment (51% cov)with 5% probability of failure (HCLPF)

Page 53: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

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LBB Margins at Constant Load(margin required :ABS Load combination =1

4.894.134.123.824.123.424.914.15PDL

3.933.473.413.201.962.984.203.63SGO

2.532.602.532.401.512.243.012.65SGI

J-TR6 ruptureR6 init.NSC

Deterministic

Probabilistic

Margins calculated at 50% confidence moment (51% cov)with 1% probability of failure (HCLPF)

Page 54: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

54

Hazard Curve for TAPP

1.E-05

1.E-03

1.E-01

1.E+01

0 0.02 0.04 0.06 0.08 0.1 0.12 0.14 0.16 0.18 0.2

PGA g

AEP

AEP: Annual Exceedance Probability

PGA: Peak Ground Acceleration

Page 55: Probabilistic Leak Before Break of 540 MW Tarapur :3/4 PHWR

55

Earthquake Induced Probabilityof Failure

• Probability of DEGB induced by earthquake isextremely low.

• It is consistent with the pipe tests conducted atBARC and international test experience that ifmaterial is ductile then maximum load can beapproximated by NSC formula

• Probability of crackinitiation (per year)

5.71X10-09PDL1.07X10-07SGO7.91E10-07SGI

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56

Discussion on Reliability StudiesPerformed at Constant Load

• Margins required on load for LBB qualification areobtained using probabilistic analysis

• Probability of DEGB of PHT pipe with LSC under DBAload is extremely low

• Mode of failure from experiments• Pipe sizes = 8” NB : NSC• Pipe sizes > 8” NB : J-Tearing

• Probability of stable crack growth initiation is also verylow.

• The reliability calculations were done using a number ofmethods, (FORM, SORM, Monte Carlo based etc.) All ofthem gave consistent results

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57

Thank You…