12/2/14 - 12/5/14, update on scc cgr testing of alloy 690 ... · update on scc cgr testing of alloy...
TRANSCRIPT
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
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
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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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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
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Fracture surface of non cold-worked Alloy 690
Facets (TG) and, occasionally, striations (environmental fatigue)
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SCC response of non cold-worked Alloy 690
Unlike the alloy in the as-received condition, the HAZ shows some IG
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
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
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
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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
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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)
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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
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
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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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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Alloy 690 Plate (Heat NX3297HK12): Specimen A690WC-AR-SL-5
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Last region on the test, TG cracking
Alloy 690 Plate (Heat NX3297HK12): Specimen A690WC-AR-SL-5
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TG cracking, cracked inclusions
Alloy 690 Plate (Heat NX3297HK12): Specimen A690WC-AR-SL-5
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Some smooth facets, perhaps some IG (not unambiguous)
Alloy 690 Plate (Heat NX3297HK12): Specimen A690WC-AR-SL-5
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Some smooth facets, perhaps some IG (not unambiguous)
Alloy 690 Plate (Heat NX3297HK12): Specimen A690WC-AR-SL-5
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Striations (environmental fatigue), perhaps some IG (not unambiguous)
Alloy 690 Plate (Heat NX3297HK12): Specimen A690WC-AR-SL-5
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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
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
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
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Alloy 690 CRDM (Sumitomo): Specimen S690-CR-1
Initial CF testing, low enhancement No IG cracking, some off-plane growth
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Alloy 690 CRDM (Sumitomo): Specimen S690-CR-1
Final CF testing, high enhancement Striations No (unambiguous) IG cracking
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Alloy 690 CRDM (Sumitomo): Specimen S690-CR-1
Final CF testing, high enhancement Striations No IG cracking
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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
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
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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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
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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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
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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)