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Task 3: Cracking of Nickel Alloys and Welds – CGRs of Alloys 600 and 690 in PWR Water Work sponsored by the US Nuclear Regulatory Commission September 25-26, 2007 Nuclear Engineering Division Argonne National Laboratory, Argonne, IL 60439 Investigators: Bogdan Alexandreanu, Omesh Chopra, Bill Soppet, and Bill Shack Experimental Effort: Ed Listwan and Loren Knoblich

09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

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Page 1: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

Task 3: Cracking of Nickel Alloys and Welds –CGRs of Alloys 600 and 690 in PWR Water

Work sponsored by the US Nuclear Regulatory Commission

September 25-26, 2007Nuclear Engineering DivisionArgonne National Laboratory, Argonne, IL 60439

Investigators: Bogdan Alexandreanu, Omesh Chopra, Bill Soppet, and Bill Shack

Experimental Effort: Ed Listwan and Loren Knoblich

Page 2: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

2Work sponsored by the US Nuclear Regulatory Commission

Outline

Experiment

CGR of Nozzle #3 Alloy 600 from Davis-Besse

CGR of Alloy 690

Page 3: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

3Work sponsored by the US Nuclear Regulatory Commission

Experiment

Temp: 320°C PWR Water (<10 ppb DO, 1000 ppm B, 2 ppm Li, ≈2 ppm hydrogenFlow Rate: ≈55 mL/minConductivity: ≈20 µS/cmLoading sequence chosen to facilitate the transition from transgranular fatigue cracking to intergranular SCC cracking:

- Precracking carried out in the PWR environment - Load Ratio R: 0.3–precrack;

0.5-0.7–sawtooth with up to 1000s rise time; 1.0–constant load

Page 4: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

4Work sponsored by the US Nuclear Regulatory Commission

The Analysis of Cyclic CGR Data for Ni-alloys

Superposition model (Kassner & Shack)

( )0.337air CF air aira a a 4.4 10 a−+ = + × ⋅

env air CF SCCa a a a= + +

SCC thref

Q 1 1a exp (K K )R T T

β⎡ ⎤⎛ ⎞= α − − −⎢ ⎥⎜ ⎟

⎢ ⎥⎝ ⎠⎣ ⎦

For Alloy 600:

10-12

10-11

10-10

10-9

10-8

10-12 10-11 10-10 10-9 10-8C

GR

env

CGRair

Page 5: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

5Work sponsored by the US Nuclear Regulatory Commission

Cracking of Nozzle Alloy 600 from Davis-Besse

Page 6: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

6Work sponsored by the US Nuclear Regulatory Commission

CGR of Nozzle #3 Alloy 600 from Davis-Besse

Specimens tested in 316°C simulated primary water:

1/4T-CTN3CL-1N3CC-2

1/2T-CTN3CC-3

L Orientation

L Orientation63.5 mm

16 mm

C Orientation

Page 7: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

7Work sponsored by the US Nuclear Regulatory Commission

Fracture surface of specimen N3CL-1

Completely IG fracture right from the notch

Page 8: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

8Work sponsored by the US Nuclear Regulatory Commission

Fracture surface of specimen N3CL-4

Completely IG fracture right from the notch

Page 9: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

9Work sponsored by the US Nuclear Regulatory Commission

Fracture surface of specimen N3CC-2

Completely IG fracture right from the notch

Page 10: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

10Work sponsored by the US Nuclear Regulatory Commission

Fracture surface of specimen N3CC-2

Completely IG fracture right from the notch

Page 11: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

11Work sponsored by the US Nuclear Regulatory Commission

Fracture surface of specimen N3CC-3

Did not start as IG fracture right from the notch, elements of IG are present in the TG region

Page 12: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

12Work sponsored by the US Nuclear Regulatory Commission

Cyclic CGRs for Nozzle #3 Alloy 600 from Davis-Besse

10-12

10-11

10-10

10-9

10-8

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

N3CL-01N3CC-02

N3CC-03

CG

Ren

v (m

/s)

CGRair (m/s)

Alloy 600 (Heat M3935)(Davis Besse CRDM Nozzle #3)316°C PWR Water

CGRair + 6.6 x 10–7(CGRair)0.33

1/4–T CT Specimen

1/2–T CT Specimen

Including SCC rateat Kmax = 17 MPa m1/2

Cyclic CGRs show environmental enhancement

Page 13: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

13Work sponsored by the US Nuclear Regulatory Commission

SCC CGRs for Nozzle #3 Alloy 600 from Davis-Besse vs. K

10-12

10-11

10-10

10-9

10 15 20 25 30 35 40 45 50

N3CC-02

N3CC-03

Exp

erim

enta

l CG

R (m

/s)

Stress Intensity K (MPa·m1/2)

Alloy 600 (Heat M3935)(Davis Besse CRDM Nozzle #3)316°C PWR Water

Median Alloy 600 at 316°C

Proposed Disposition Curve75th Percentile

Alloy 600 at 316°C

1/4–T CT Specimen

1/2–T CT Specimen

SCC CGRs are 2-4× the proposed disposition curveHeat ranks at 95% of the distribution (26 heats)

0.0

0.2

0.4

0.6

0.8

1.0

10-13 10-12 10-11 10-10

Alloy 600 HeatsD–B Nozzle #3

Cum

ulat

ive

Dis

tribu

tion

F

Constant α at 325°C

75th Percentile

50th Percentile

25th Percentile

α = 1.44 x 10-12

α = 2.98 x 10-12

α = 6.96 x 10-13

Page 14: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

14Work sponsored by the US Nuclear Regulatory Commission

Nozzle #3 Alloy 600 from Davis-Besse – Summary and Remaining Issues

Very high crack growth ratesIG fracture mode during precracking

Very high SCC CGRs unexpected because:Alloy with average strengthGrain boundary carbide coverage (50–60%)

More recent investigations Good grain boundary carbide coverage Low special boundary fractions- could explain the high SCC CGRs- can not explain IG fracture mode during precracking

0

100

200

300

400

500

600

700

0 10 20 30 40 50 60 70

N3TL-1N3TL-2N3TL-3

Stre

ss (M

Pa)

Strain (%)

Alloy 600 CRDM Nozzle #3316°C

Page 15: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

15Work sponsored by the US Nuclear Regulatory Commission

Stress Corrosion Cracking of Alloy 690

Page 16: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

16Work sponsored by the US Nuclear Regulatory Commission

Alloy 690 specimens

<0.010.010.4730.8259.670.040.020.0030.0018.530.330.04ANL

29.559.50.010.07<0.0019.90.200.03VendorA 690WC (NX3297HK12)

CoNbTiCrNiCuSiPSFeMnCAnalysisAlloy ID (Heat)

Alloy 690 in plate form (MIL-DTL-24802∗)

Cold-rolled in three passes to achieve approx. 26% reduction in thicknessSpecimens cut in both SL and ST orientations

Approx 1.5”

3.5”

17”

rolling direction

1 2 3 4

∗MIL-DTL-24802- vacuum induction - melted - electro slag - removed - hot - rolled - de-scaled- annealed at 1900F for 2h- air-cooled

Page 17: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

17Work sponsored by the US Nuclear Regulatory Commission

Results - Alloy 690 specimen A690WC-SL-1

13.00

13.20

13.40

13.60

13.80

14.00

10

20

30

40

50

60

70

80

400 800 1200 1600 2000 2400 2800

Cra

ck L

engt

h (m

m)

K max

(MP

a m

0.5 )

Time (h)

Alloy 690Specimen # A690WC-SL-1320°C, Simulated PWR Water

71.46 x 10–11 m/s26.7 MPa m0.5

Constant Load

63.63 x 10–10 m/s26.2 MPa m0.5

0.50, Rise time = 1000 s

Kmax

8

10

Crack Length

92.83 x 10–11 m/s28.0 MPa m0.5

Constant Load

Crack lengthKmax

Page 18: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

18Work sponsored by the US Nuclear Regulatory Commission

Results - Alloy 690 specimen A690WC-ST-1

13.00

13.20

13.40

13.60

13.80

14.00

14.20

14.40

20

25

30

35

40

45

50

55

60

2600 2800 3000 3200 3400 3600 3800 4000

Cra

ck L

engt

h (m

m)

Km

ax (M

Pa

m0.

5 )

Time (h)

Kmax

Crack Length

Alloy 690Specimen # A690WC-ST-1320°C, Simulated PWR Water

12

Period 133.3 x 10–11 m/s31 MPa m0.5

Constant Load

Page 19: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

19Work sponsored by the US Nuclear Regulatory Commission

Fracture surface of A690WC-SL-1

Page 20: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

20Work sponsored by the US Nuclear Regulatory Commission

Fracture surface of A690WC-ST-1

Page 21: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

21Work sponsored by the US Nuclear Regulatory Commission

Fracture surface of A690WC-SL-1

Page 22: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

22Work sponsored by the US Nuclear Regulatory Commission

Fracture surface of A690WC-SL-1

Page 23: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

23Work sponsored by the US Nuclear Regulatory Commission

Cyclic CGR data for Alloy 690 and Davis-Besse Alloy 600

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-11/4-T CT DB N3CC-2A690WC-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

Page 24: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

24Work sponsored by the US Nuclear Regulatory Commission

SCC CGRs for Alloy 690 and Davis-Besse Alloy 600 vs. K

10-12

10-11

10-10

10-9

10 15 20 25 30 35 40 45 50

DB N3CC-2DB N3CC-3A690WC-SL-1A690WC-ST-1

Exp

erim

enta

l CG

R (m

/s)

Stress Intensity K (MPa·m1/2)

Alloy 600325°C

CGR Curve Alloy 60075th Percentile α

Alloy 60050th Percentile α

Page 25: 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 ... · aa a 4.410 aair CF air air +=+× ... 09/25/2007 - 09/26/2007 Meeting Presentation on Task 3 - Part 4: Cracking of Nickel

25Work sponsored by the US Nuclear Regulatory Commission

Summary

Nozzle #3 Alloy 600 from Davis-BesseFracture is predominantly IG, even during mechanical fatigue loading Cyclic CGRs show environmental enhancement in PWR water at 316°C SCC CGRs are a factor of 2-4 higher than the proposed disposition curve for Alloy 600; growth rates correspond to 95th percentile of the data

Alloy 690Fracture surfaces were uniform for both Alloy 690 specimens Cyclic CGRs of Alloy 690 show environmental enhancement The SCC CGRs in simulated PWR water at 320°C were as high as:

2.8-3.3 x 10-11 m/s for Kmax = 28-31 MPa m1/2 for Alloy 6905.4 x 10-11 m/s for Kmax = 30.2 MPa m1/2 for Alloy 152