12/2/14 - 12/5/14, update on scc cgr testing of alloy 690 ... · update on scc cgr testing of alloy...

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Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission Bogdan Alexandreanu, Yiren Chen, Ken Natesan and Bill Shack Argonne National Laboratory NRC Project Manager: Greg Oberson Alloy 690 Expert Panel Meeting Tampa, FL December 2-5, 2014

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Page 1: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Update on SCC CGR testing of Alloy 690(non cold-worked conditions)

Work sponsored by the US Nuclear Regulatory Commission

Bogdan Alexandreanu, Yiren Chen, Ken Natesan and Bill Shack

Argonne National Laboratory

NRC Project Manager: Greg Oberson

Alloy 690 Expert Panel Meeting

Tampa, FL

December 2-5, 2014

Page 2: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 2

Presentation Outline

Background and experimental approach

Results:- Alloy 690 MA in plate form - Alloy 690 TT CRDM (Valinox, Sumitomo)

Summary

Page 3: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 3

Cyclic response – Alloy 690 in the CW and the as-received conditions

Alloy 690 26% cold work: environmental enhancement as high as D-B nozzle #3 Alloy 690 26% cold work: environmental enhancement much higher than as-received condition

10-11

10-10

10-9

10-8

10-7

10-11 10-10 10-9 10-8 10-7

1/2-T CT DB N3CC-31/4-T CT DB N3CL-1A690WC-SL-1A690WC-ST-1

CG

Ren

v (m

/s)

CGRair (m/s)

Alloy 690 and Davis-Besse N#3 Alloy 600Simulated PWR Water

Best-Fit Curve for Davis-Besse N#3 A600CGRair + 6.6 x 10–7(CGRair)

0.33

10-12

10-11

10-10

10-9

10-8

10-7

10-12 10-11 10-10 10-9 10-8 10-7

26% CR, A690WC-SL-126% CR, A690WC-ST-1C690-CR-1C690-LR-2

CG

Ren

v (m/s

)CGRair (m/s)

Alloy 690Simulated PWR Water at 320°C

Best-Fit Curve for Alloy 600CGRair + 4.4 x 10–7(CGRair)

0.33

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Work sponsored by the US Nuclear Regulatory Commission 4

SCC response of non cold-worked Alloy 690 and 690HAZ

Alloy 690 very low SCC CGRs Alloy 690HAZ SCC CGRs are perhaps slightly higher

10-13

10-12

10-11

10-10

10-9

10 15 20 25 30 35 40 45 50

C690-LR-2C690-CR-1HAZ, CF690-CR-1HAZ, CF690-CR-3

Expe

rimen

tal C

GR

(m/s

)

Stress Intensity K (MPa·m1/2)

Alloy 690 and 690 HAZSimulated PWR environment320°C

MRP-55Alloy 600

75 Percentile

Solid symbols: CL

Page 5: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 5

Fracture surface of non cold-worked Alloy 690

Facets (TG) and, occasionally, striations (environmental fatigue)

Page 6: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 6

SCC response of non cold-worked Alloy 690

Unlike the alloy in the as-received condition, the HAZ shows some IG

Page 7: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 7

Bill Mills et al (Env Deg 2009)

Bill Mills reports “substantial” IG engagement: 9% for tR= 30s, and 20% for tR= 600s under continuous cyclic at ∆K = 12 MPa m1/2 in DPW at 288ºC

No IG engagement for ∆K > 16 MPa m1/2

Page 8: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 8

Corrosion fatigue work by Bill Mills et al (Env Deg 2009)

Bettis data show higher enhancement than ANL DPW (<5 ppb) ANL DPW (<5 ppb data) were all obtained with short rise times, tR = 12 seconds

Page 9: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 9

Excellent agreement between current ANL data (solid blue) and Bettis data (red) on time domain plots (left plot)

Corrosion fatigue work by Bill Mills et al (Env Deg 2009)

10-9

10-8

10-7

10-6

10-5

10-9 10-8 10-7 10-6 10-5

C690-CR-1

C690-LR-2

Alloy 690Simulated PWR Water at 320°C

Page 10: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 10

Experimental Approach

1.0

2.0

3.0

4.0

5.0

6.0

7.0

5 10 15 20 25

C690-LR-2C690-CR-1

Alloy 690Simulated PWR Water at 320°C

CG

Ren

v/CG

Rai

r

K (MPa·m 1/2)

BM

Opt

imum

IG

BM

No

IG

Bill Mills “optimum”: ∆K = 12 MPa m1/2 , tR= 600s (da/dN = 5E-8 m/s), GGRenv/CGRair ~ 6 No IG engagement for ∆K > 16 MPa m1/2

R=0.5, 600/12 (∆K = 14-15 MPa m1/2) was used extensively at ANL for transitioning; for welds at 320ºC, da/dN = 3.8E-8 m/s

Page 11: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 11

Alloy 690 Plate (Heat NX3297HK12)

Tested and cracked at ANL in 2005-2006 in 26% cold-rolled condition Subsequently tested worldwide Also known as “ANL plate” or “rogue heat” (J. Hickling)

A690WC-AR-SL-5(5 mm from surface)

Page 12: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 12

Alloy 690 Plate (Heat NX3297HK12): Specimen A690WC-AR-SL-5

Heat NX3297HK12 very resistant to fatigue (as resistant as Alloy 600) Environmental enhancement is minimal

10-12

10-11

10-10

10-9

10-8

10-7

10-12 10-11 10-10 10-9 10-8 10-7

CGR air 600 (NUREG-6721)CGR env 600 (NUREG-4667)Alloy 690 AR (A690WC-AR-SL-5)

CG

Ren

v (m

/s)

CGRair (m/s)

Alloy 690 Heat NX3297HK12Simulated PWR Water at 320°C Best-Fit Curve for Alloy 600CGRair + 4.4 x 10–7(CGRair)

0.33

R=0.1

Page 13: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 13

1.0

2.0

3.0

4.0

5.0

6.0

7.0

5 10 15 20 25

A690WC-AR-CL-5C690-LR-2C690-CR-1

Alloy 690Simulated PWR Water at 320°C

CG

Ren

v/C

GR

air

K (MPa·m1/2)

BM O

ptim

um IG

BM N

o IG

12

3

4

5

CGRair = ct. (3E-11 m/s) da/dN < 2E-8 m/cycle (BM = 5E-8 m/cycle) Environmental enhancement is minimal (less than the Valinox CRDM in

LR orientation) and flat (does not seem to show the ∆K dependence)

Alloy 690 Plate (Heat NX3297HK12): Specimen A690WC-AR-SL-5

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Work sponsored by the US Nuclear Regulatory Commission 14

28.400

28.450

28.500

28.550

40

45

50

55

60

65

70

75

80

4800 4900 5000 5100 5200 5300 5400 5500 5600Time (h)

Specimen A690WC-AR-SL-5PWR environment

Cra

ck L

engt

h (m

m)

Km

ax (M

Pa

m0.

5 )

Kmax

Crack Length

Period 301.1 x 10–11 m/s51.2 MPa m0.5

R=0.7., 1200/12 + 2h

P30: Response from cycle + hold is at the air line (1.04E-11), SCC CGR component is “zero”.

Alloy 690 Plate (Heat NX3297HK12): Specimen A690WC-AR-SL-5

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Work sponsored by the US Nuclear Regulatory Commission 15

P31: “No growth” condition confirmed at constant load The “rogue heat” did not live up to its reputations or SCC in a cold-worked

condition is not a good predictor for the SCC behavior of the as-received alloy

28.460

28.480

28.500

28.520

28.540

40

45

50

55

60

65

70

75

80

5400 5600 5800 6000 6200 6400 6600 6800Time (h)

Specimen A690WC-AR-SL-5PWR environment

Cra

ck L

engt

h (m

m)

Km

ax (M

Pa

m0.

5 )

Kmax

Crack Length

Period 31no growth

51.5 MPa m0.5

Constant load

Alloy 690 Plate (Heat NX3297HK12): Specimen A690WC-AR-SL-5

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Work sponsored by the US Nuclear Regulatory Commission 16

Alloy 690 Plate (Heat NX3297HK12): Specimen A690WC-AR-SL-5

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Work sponsored by the US Nuclear Regulatory Commission 17

Last region on the test, TG cracking

Alloy 690 Plate (Heat NX3297HK12): Specimen A690WC-AR-SL-5

Page 18: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 18

TG cracking, cracked inclusions

Alloy 690 Plate (Heat NX3297HK12): Specimen A690WC-AR-SL-5

Page 19: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 19

Some smooth facets, perhaps some IG (not unambiguous)

Alloy 690 Plate (Heat NX3297HK12): Specimen A690WC-AR-SL-5

Page 20: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 20

Some smooth facets, perhaps some IG (not unambiguous)

Alloy 690 Plate (Heat NX3297HK12): Specimen A690WC-AR-SL-5

Page 21: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 21

Striations (environmental fatigue), perhaps some IG (not unambiguous)

Alloy 690 Plate (Heat NX3297HK12): Specimen A690WC-AR-SL-5

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Work sponsored by the US Nuclear Regulatory Commission 22

Alloy 690 CRDM (Sumitomo): Specimen S690-CR-1

10-12

10-11

10-10

10-9

10-8

10-7

10-12 10-11 10-10 10-9 10-8 10-7

Alloy 690 AR CRDM (C690-CR-1)

Alloy 690 AR CRDM (S690-CR-1)

CG

Ren

v (m

/s)

CGRair (m/s)

Alloy 690 CRDMSimulated PWR Water at 320°C

Best-Fit Curve for Alloy 600CGRair + 4.4 x 10–7(CGRair)

0.33

Identical fatigue and corrosion fatigue response to that of the ValinoxCRDM

Page 23: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 23

1.0

2.0

3.0

4.0

5.0

6.0

7.0

5 10 15 20 25

A690WC-AR-CL-5C690-LR-2C690-CR-1S690-CR-1

Alloy 690Simulated PWR Water at 320°C

CG

Ren

v/C

GR

air

K (MPa·m1/2)

BM O

ptim

um IG

BM N

o IG

45

6

7

16

Alloy 690 CRDM (Sumitomo): Specimen S690-CR-1

CGRair = ct. (3E-12 m/s) da/dN < 2E-8 m/cycle (BM = 5E-8 m/cycle) Environmental enhancement shows max at ∆K = 12 MPa m1/2

Page 24: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 24

Alloy 690 CRDM (Sumitomo): Specimen S690-CR-1

P19: Environmental enhancement was not maintained when the 4h hold was introduced

P19: Response from cycle + hold is at the air line (1.04E-11), SCC CGR component is “zero”

P20: Confirmed at constant load

14.510

14.520

14.530

14.540

14.550

14.560

14.570

20

40

60

80

100

5000 5500 6000 6500Time (h)

Specimen S690-CR-1PWR environment

Cra

ck L

engt

h (m

m)

K max

(MPa

m0.

5 )

Period 20no growth

34.7 MPa m0.5

Constant load

Kmax

Crack Length

Period 191.34 x 10–12 m/s34.7 MPa m0.5

R=0.63, 7000/12 + 4h

Page 25: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 25

Alloy 690 CRDM (Sumitomo): Specimen S690-CR-1

Initial CF testing, low enhancement No IG cracking, some off-plane growth

Page 26: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 26

Alloy 690 CRDM (Sumitomo): Specimen S690-CR-1

Final CF testing, high enhancement Striations No (unambiguous) IG cracking

Page 27: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 27

Alloy 690 CRDM (Sumitomo): Specimen S690-CR-1

Final CF testing, high enhancement Striations No IG cracking

Page 28: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 28

Alloy 690 MA plate (Allvac): Specimen B25K

10-12

10-11

10-10

10-9

10-8

10-7

10-12 10-11 10-10 10-9 10-8 10-7

Alloy 690 AR (B25K)Alloy 690 AR (A690WC-AR-SL-5)

CG

Ren

v (m/s

)

CGRair (m/s)

Alloy 690 PlateSimulated PWR Water at 320°C Best-Fit Curve for Alloy 600CGRair + 4.4 x 10–7(CGRair)

0.33

R=0.1

CGRair = ct. (3E-12 m/s) da/dN < 3E-8 m/cycle (BM = 5E-8 m/cycle) Environmental enhancement shows max at ∆K = 12 MPa m1/2

Page 29: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 29

1.0

2.0

3.0

4.0

5.0

6.0

7.0

5 10 15 20 25

C690-LR-2C690-CR-1A690WC-AR-CL-5S690-CR-1B25K

Alloy 690Simulated PWR Water at 320°C

CG

Ren

v/C

GR

air

K (MPa·m1/2)

BM O

ptim

um IG

BM N

o IG

45

6

7

16

34

56

7

CGRair = ct. (3E-12 m/s) da/dN < 3E-8 m/cycle (BM = 5E-8 m/cycle) Environmental enhancement builds-up eventually reaching that observed

for CRDM materials (∆K = 12 MPa m1/2)

Alloy 690 MA plate (Allvac): Specimen B25K

Page 30: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission

Experimental approach

30

Alternating hold between Kmin and Kmax = turns SCC “off” and “on” SCC CGR = difference between the two rates Maintain cycling longer

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Work sponsored by the US Nuclear Regulatory Commission 31

Maintain cycling for longer periods of time Environmental enhancement was maintained (unlike the S690 CRDM) SCC CGR = difference between the two rates = 1E-12 m/s

19.300

19.350

19.400

20

25

30

35

40

45

50

55

60

2000 2500 3000 3500 4000Time (h)

Specimen B25KPWR environment

Cra

ck L

engt

h (m

m)

K max

(MP

a m

0.5 )

Kmax

Crack Length

Period 86.20 x 10–12 m/s35.0 MPa m0.5

R=0.63, 6000/12 + 4h at Kmin

Period 97.3 x 10–12 m/s35.0 MPa m0.5

R=0.63, 6000/12 + 4h

Alloy 690 MA plate (Allvac): Specimen B25K

Page 32: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 32

Summary

Tried experimental approach based on Bill Mill’s experience(very similar to ANL’s practice)

Environmental enhancement depends on ∆K, and has a maximum at ∆K = 12 MPa m1/2

Despite the optimized conditions, the SCC CGRs for as-received Alloy 690 are extremely low or “zero”

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Work sponsored by the US Nuclear Regulatory Commission 33

Alloy 690TT Specimens (as received condition)

Alloy 690TT CRDM tubing, 2541 – Heat WP142- specimen designation: C690 - 1/2T-CT specimens were cut from tubing (in as-received condition) in CR and LR orientations

LR

CR

Page 34: 12/2/14 - 12/5/14, Update on SCC CGR testing of Alloy 690 ... · Update on SCC CGR testing of Alloy 690 (non cold-worked conditions) Work sponsored by the US Nuclear Regulatory Commission

Work sponsored by the US Nuclear Regulatory Commission 34

Excellent agreement between current ANL data (solid blue) and Bettis data (red) on time domain plots (left plot)

10-9

10-8

10-7

10-6

10-5

10-9 10-8 10-7 10-6 10-5

C690-CR-1

C690-LR-2

Alloy 690Simulated PWR Water at 320°C

Corrosion fatigue work by Bill Mills et al (Env Deg 2009)