june 2011. - nuclear regulatory commissionjune 6-7, 2011 bogdan alexandreanu, yiren chen, ken...
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Update on SCC CGR tests on Alloys 690/52/152 at ANL – June 2011
Work sponsored by the US Nuclear Regulatory Commission
US NRC/EPRI Meeting
Rockville, MD
June 6-7, 2011
Bogdan Alexandreanu, Yiren Chen, Ken Natesan and Bill Shack
Argonne National Laboratory
2Work sponsored by the US Nuclear Regulatory Commission
Presentation Topics
Experimental approach
SCC of 52M/182 WOL
SCC of Alloy 152 Weld
SCC of Alloy 690 HAZ
3Work sponsored by the US Nuclear Regulatory Commission
Experimental Approach - Transitioning to SCC
ANL approach very similar to the widely-used method (increasing R and decreasing frequency) but with a few differences:
- Precracking is always conducted in the environment1
- Use of slow/fast sawtooth with increasing rise times- Loading takes into account possible K and Kth effects2
- Monitor specimen response- Calculate cyclic CGRs based on rise time3
- Monitor cyclic rates for environmental enhancement 4
- Attempt to transition only from those conditions that showenvironmental enhancement
1 Provides (essential) baseline cyclic data2 K/Kth effects have been observed/formulated for Alloy 6903 Well-characterized cyclic CGR also enables the calculation of the SCC component for periods
with hold times or constant load with periodic unloading4 Accomplished by plotting the measured in the environment vs. the rates that would be
expected in air under the same loading conditions
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The Analysis of Cyclic CGR Data
Superposition model (Kassner & Shack)
0.78air CF air aira a a 0.018 a
env air CF SCCa a a a
SCCref
Q 1 1a exp KR T T
*For Ni-welds:
10-12
10-11
10-10
10-9
10-8
10-7
10-6
10-12 10-11 10-10 10-9 10-8 10-7 10-6C
GR
env
CGRair
CGRair + 0.018 (CGRair)0.78
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Expected behavior of cyclic rates: Alloys 600, 690, Ni-Alloy Weld
10-11
10-10
10-9
10-8
10-7
10-11 10-10 10-9 10-8 10-7
CGR env 600 (NUREG-4667)CGR air 690 (NUREG-6383)CGR air weld (NUREG-6921)CGR env weld (NUREG-6921)
CG
Ren
v (m
/s)
CGRair (m/s)
CGR env Ni-weld
CGR env 600
CGR air 600
CGR air 690
CGR air Ni-weld
Correlations established at ANL for a variety of alloys Fatigue behavior is highly reproducible
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Alloy 52M/182 Weld Overlay
Alloy 182 weld tested previously (without the WOL) Alloy 52M (Special Metals, Heat NX75W1TK ) welded at ANL Central Shops using
parameters used by industry CGR test objective: attempt to transition an SCC crack from Alloy 182 into 52M
Alloy 600
Alloy 182
1
Alloy 52M
18252M
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Alloy 52M/182 Weld Overlay – Summary of SCC CGR data vs. distance to the interface
SCC CGRs decrease as the crack approaches the interface, continues to decrease past the interface
Control cyclic rates mirror the SCC behavior
182 52M
10-12
10-11
10-10
10-9
-2.0 -1.0 0.0 1.0 2.0 3.0
8
SCC CGR (CL, CL + pu)est SCC CGR (cycle + hold)Control cycle
CG
R (m
/s)
Distance from the 52M WOL interface (mm)
Alloy 182 Alloy 52M
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Alloy 52M/182 WOL – Fracture Surface 1
Partial (40%) growth into Alloy 52M Areas A + B: average growth 0.35 mm, average CGR 3 10-11 m/s
(consistent with DC potential) Area B: max growth 2.5 mm, max CGR 2 10-10 m/s
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Alloy 52M/182 WOL – Crack Transition from Alloy 182 to Alloy 52M(region A)
No change in fracture mode at the interface
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Alloy 52M/182 WOL – Crack Transition from Alloy 182 to Alloy 52M(region B)
No change in fracture mode at the interface
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Alloy 52M/182 Weld Overlay – test in progress (A52M-182-TS-1)
Objective: confirm behavior observed in the previous test 1T CT specimen in similar (TS) orientation, initial notch 8.2 mm from the interface
182
52M
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Alloy 52M/182 Weld Overlay – test in progress (A52M-182-TS-1)
Cyclic rates similar to those obtained previously on the same weld (without the Alloy 52M WOL)
SCC CGR similar approx. 2 mm from the interface
10-12
10-11
10-10
10-9
10-8
10-7
10-12 10-11 10-10 10-9 10-8 10-7
A52M-182-TS-1A52M-182-TS-3A182-TS-1
CG
Ren
v (m
/s)
CGRair Ni-weld alloys (m/s)
Alloy 182 WeldSimulated PWR Water at 320°C
Best Fit Curve for Alloy 182CGRair + 0.018 (CGRair)
0.78
10-12
10-11
10-10
10-9
10 15 20 25 30 35 40
A182-TS-1A52M-182-TS-3A52M-182-TS-1
Exp
erim
enta
l CG
R (m
/s)
Stress Intensity K (MPa·m1/2)
Alloy 52M/182 WOL320°C
ProposedDisposition Curve
for Alloy 182 Weld (MRP-115)
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Alloy 52M/182 Weld Overlay – test in progress (A52M-182-TS-1)
SCC CGRs decrease as the crack approaches the interface Error bars: 20% uncertainty in DC potential measurements
10-12
10-11
10-10
10-9
-3.0 -2.0 -1.0 0.0 1.0 2.0 3.0
8
A52M-182-TS-3 (CL, CL + pu)A52M-182-TS-3 (cycle + hold)A52M-182-TS-1 (CL + pu)
CG
R (m
/s)
Distance from the 52M WOL interface (mm)
Alloy 182 Alloy 52M
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Alloy 52M/182 Weld Overlay – key findings and future tests
Substantial growth (0.7 mm) in Alloy 52M in a direction parallel to the interface Crack appearance (branching) suggests an IG fracture mode
Crack propagation First test (A52M-182-TS-3): Interaction with the interface a concern
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Alloy 52M/182 WOL – fractured specimen A52M-182-TS-3
Growth along the interface appears more severe than initially thought (based on the cross section): 2.2 mm (3000h), CGR 2 10-10 m/s
16Work sponsored by the US Nuclear Regulatory Commission
Alloy 52M/182 Weld Overlay – dilution specimens
182
52M
152 butter
LAS
CT specimens aligned along the 52M/182 and 152/LAS
17Work sponsored by the US Nuclear Regulatory Commission
Alloy 52M/182 WOL - Summary
Tests were initiated in Alloy 182, and both cyclic and SCC known conditions were reproduced
The 52M/182 interface seems to affect crack propagation in Alloy 182 ahead of the interface:- both SCC CGRs and environmental enhancement of cyclic rates decreased
First completed test (emerging issues):
Alloy 52M is susceptible to IG SCC, CGRs 10-11 m/s (consistent with Alloy 152 in IG fracture mode)
Alloy 52M seems highly susceptible to cracking along the interface (SCC CGRs 10-10 m/s) – the effect of dilution will be addressed in future ANL tests
18Work sponsored by the US Nuclear Regulatory Commission
Alloy 152 Welds
New weld: same Alloy 152 heat WCO4F6 (152, 1/8) as the previous weld Welding procedure was qualified to ASME IX 1-T CT specimens cut in similar fashion, TS orientation Similar CGR testing conditions (320C, 23 cc/kg H)
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Alloy 152 Weld specimen N152-TS-1
20Work sponsored by the US Nuclear Regulatory Commission
Alloy 152 specimen N152-TS-1 – in-situ precracking
Objectives: Create a sharp crack tip Confirm the expected fatigue behavior for the specimen
- high frequency (>0.5 Hz) establishes the baseline “air” curve - consistent fatigue data ensures the straightness of the crack front
12.50
13.00
13.50
14.00
14.50
15.00
15.50
16.00
0
20
40
60
80
100 200 300 400 500 600Time (h)
Kmax
Crack Length
Pre a
Pred
Pref
Prej
Prel
Pren
Prer
1Alloy 152Specimen # N152-TS-1PWR environment
Cra
ck L
engt
h (m
m)
Km
ax (M
Pa
m0.
5 )
21Work sponsored by the US Nuclear Regulatory Commission
Alloy 152 specimen N152-TS-1
Known fatigue and corrosion fatigue behavior (analysis based on 129 tests in air and water, NUREG-6921) reproduced, 3x environmental enhancement
R=0.5, 600/12 was chosen as transitioning condition, CGRair 6 10-11 m/s*,close to expected SCC CGR, hence, will preserve IG SCC behavior*at K=30 MPa m1/2, 350°C, CGRair 1.5 10-10 m/s
10-11
10-10
10-9
10-8
10-7
10-11 10-10 10-9 10-8 10-7
N152-TS-1
CG
Ren
v (m
/s)
CGRair Ni-weld alloys (m/s)
Alloy 152 WeldSimulated PWR Water at 320°C
Best Fit Curve for Alloy 182CGRair + 0.018 (CGRair)
0.78
10-11
10-10
10-9
10-8
10-7
10-11 10-10 10-9 10-8 10-7
N152-TS-1A152-TS-2A152-TS-4A152-TS-5
CG
Ren
v (m
/s)
CGRair Ni-weld alloys (m/s)
Alloy 152 WeldSimulated PWR Water at 320°C
Best Fit Curve for Alloy 182CGRair + 0.018 (CGRair)
0.78
22Work sponsored by the US Nuclear Regulatory Commission
Alloy 152 specimen N152-TS-1
Ligaments pose a problem early on (good news) CL + PU (either 2h or 1h) too gentle Start and end by reproducing known conditions IG SCC fracture mode is suspected – must be preserved (use R=0.5, 600/12 )
16.20
16.25
16.30
16.35
16.40
0
20
40
60
80
2200 2400 2600 2800 3000Time (h)
Kmax
Crack Length
Period 91.5 x 10–11 m/s26.3 MPa m0.5
R=0.5, 600/12, 2h hold
Period 101.5 x 10–11 m/s26.3 MPa m0.5
R=0.5, 600/12, 1h hold
Period 114.0 x 10–12 m/s26.3 MPa m0.5
CL + PU (2h)
Period 122.6 x 10–12 m/s26.3 MPa m0.5
CL + PU (1h)
Period 131.2 x 10–10 m/s26.8 MPa m0.5
R=0.5, 600/12
Alloy 152Specimen # N152-TS-1PWR environment
Period 81.45 x 10–10 m/s26.6 MPa m0.5
R=0.5, 600/12
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Alloy 152 specimen N152-TS-1
Period 14: average SCC CGR component 4.6 10-11 m/s(cycle + hold is actually gentler than CL + PU)
16.30
16.35
16.40
16.45
16.50
16.55
0
20
40
60
80
100
3000 3100 3200 3300 3400 3500 3600 3700Time (h)
Kmax
Crack Length
Period 131.2 x 10–10 m/s26.8 MPa m0.5
R=0.5, 600/12
Period 142.5 x 10–11 m/s26.8 MPa m0.5
R=0.5, 600/12, 2h hold
6.5 x 10–11 m/s
5.4 x 10–11 m/sAlloy 152Specimen # N152-TS-1PWR environment
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Alloy 152 specimen N152-TS-1
Previous rate confirmed at CL in test period 15 Ligaments begin to affect the crack length readings Reintroduced cycle – note the lag
16.45
16.50
16.55
16.60
16.65
15
20
25
30
3500 3600 3700 3800 3900 4000Time (h)
Kmax
Crack Length
Period 154.3 x 10–11 m/s26.8 MPa m0.5
CL
Period 145.4 x 10–11 m/s
R=0.5 600/12+ 2h
Period 161.6 x 10–10 m/s27.1 MPa m0.5
R=0.5, 600/12
Alloy 152Specimen # N152-TS-1PWR environment
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Alloy 152 specimen N152-TS-1
Attempt CL + PU (either 2h or 1h) - too gentle Start and end by reproducing known conditions (and preserve the fracture
mode)
16.50
16.55
16.60
16.65
16.70
16.75
16.80
20
30
40
50
60
3900 4000 4100 4200 4300 4400 4500Time (h)
Kmax
Crack Length
Alloy 152Specimen # N152-TS-1PWR environment Period 18
1.7 x 10–10 m/s27.3 MPa m0.5
R=0.5, 600/12Period 17negligible
27.1 MPa m0.5
CL + PU (2h)
Period 191.4 x 10–11 m/s27.3 MPa m0.5
CL + PU (2h)
Period 20negligible
27.3 MPa m0.5
CL + PU (1h)
Period 161.6 x 10–10 m/s27.1 MPa m0.5
R=0.5, 600/12
Period 211.2 x 10–10 m/s27.4 MPa m0.5
R=0.5, 600/12
26Work sponsored by the US Nuclear Regulatory Commission
Alloy 152 specimen N152-TS-1
SCC CGR consistent with those measured previously
16.65
16.70
16.75
16.80
16.85
20
30
40
50
60
4500 4600 4700 4800 4900 5000 5100 5200Time (h)
Kmax
Crack Length
Period 222.5 x 10–11 m/s27.4 MPa m 0.5
CL
Alloy 152Specimen # N152-TS-1PWR environment
Period 211.2 x 10–10 m/s27.4 MPa m 0.5
R=0.5, 600/12
27Work sponsored by the US Nuclear Regulatory Commission
The Analysis of Cyclic CGR Data for Alloy 152 –Implications for the SCC test management
10-13
10-12
10-11
10-10
10-9
10 20 30 40 50
A152-TS-2A152-TS-4A152-TS-5
Exp
erim
enta
l CG
R (m
/s)
Stress Intensity K (MPa·m1/2)
Alloy 152 Weld320°C
MRP-115 Ni-Weds
75 Percentile
MRP-115Ni-Welds
25 Percentile
y = m1 * (M0)^ 1.6ErrorValue
1.0815e-148.7892e-14m1 NA5.835e-22ChisqNA0.37161R
env air CF SCCa a a a
Need to balance the need for environmental enhancement with the optimal test condition (to measure SCC), keeping in mind the effects of R and rise time
Expected curve for the total CGR in the environment very close to the CF curve – quality mechanical and CF data for the alloy at hand becomes critical
R=0.7
R=0.5
R=0.3
10-12
10-11
10-10
10-9
10-8
10-7
10-6
10-12 10-11 10-10 10-9 10-8 10-7 10-6
CG
Ren
v (m
/s)
CGRair Ni-weld alloys (m/s)
Alloy 152 WeldSimulated PWR Water at 320°C
Best Fit Curve for Alloy 182CGRair + 0.018 (CGRair)
0.78
K = 28 MPa·m1/2
28Work sponsored by the US Nuclear Regulatory Commission
The Analysis of Cyclic CGR Data – Alloy 152env air CF SCCa a a a
Larger K (50 MPa m1/2) would certainly help, however, The need for quality mechanical and CF data for the alloy at hand remains
important
10-12
10-11
10-10
10-9
10-8
10-7
10-6
10-12 10-11 10-10 10-9 10-8 10-7 10-6
CG
Ren
v (m
/s)
CGRair Ni-weld alloys (m/s)
Alloy 152 WeldSimulated PWR Water at 320°C
Best Fit Curve for Alloy 182CGRair + 0.018 (CGRair)
0.78
K = 50 MPa·m1/2
29Work sponsored by the US Nuclear Regulatory Commission
Alloy 152 - Summary
Test in progress on the new weld:
Known fatigue and corrosion fatigue behavior were reproduced
Select loading conditions show environmental enhancement of cyclic CGRs
The SCC CGRs in simulated PWR water at 320C appear to be in the 10-11 m/s, consistent with previous results
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CRDM Alloy 690 HAZ
Alloy 152 Weld (B-P7)specimen designation C152
Alloy 690 HAZ (2541-Heat WP142, Valinox) specimen designation CF690-CR-XX
Two specimens CF690-CR-1 and CF690-CR-3: test plane parallel to the HAZ
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CF690-CR-1 Lateral surface 1
Crack seems to follow the fusion line Granular fracture mode
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CRDM Alloy 690 HAZ
Alloy 152 Weld (B-P7)specimen designation C152
Alloy 690 HAZ (2541-Heat WP142, Valinox) specimen designation CF690-CR-XX
Current approach: test plane at an angle to the HAZ
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CRDM Alloy 690 HAZ Specimen CF690-CR-3
Constant load with periodic unloading (2 h) CGR 9 10-12 m/s initially On average, CGR factor 2x higher than that for the alloy in the as-received
condition
11.930
11.940
11.950
11.960
11.970
0
10
20
30
40
50
60
70
80
400 600 800 1000 1200Time (h)
Alloy 690 HAZSpecimen # CF690-CR-4PWR environment
Kmax
Crack Length
Period 46.0 x 10–12 m/s21.8 MPa m0.5
Constant Load with PU (2h)
Cra
ck L
engt
h (m
m)
Km
ax (M
Pa
m0.
5 )8.7 x 10–12 m/s
3.2 x 10–12 m/s
Period 52.6 x 10–11 m/s21.8 MPa m0.5
R=0.5, 600/12
Period 38.3 x 10–11 m/s21.7 MPa m0.5
R=0.5, 600/12
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Cyclic CGRs for Alloy 690 HAZ vs. as-received and 26%-CR
Cyclic rates for the third specimen consitent with those measured previously; the new approach shows some promise
Environmental enhancement for Alloy 690 HAZ is similar to that for the as-received alloy Cyclic rates for Alloy 690 HAZ specimens are smaller than those for 26%-CR alloy
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-1CF690-CR-1CF690-CR-3
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
10-12
10-11
10-10
10-9
10-8
10-7
10-12 10-11 10-10 10-9 10-8 10-7
CF690-CR-1CF690-CR-3CF690-CR-4
CG
Ren
v (m
/s)
CGRair (m/s)
Alloy 690 HAZSimulated PWR Water at 320°C
Best-Fit Curve for Alloy 600CGRair + 4.4 x 10–7(CGRair)
0.33
3
5
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Cyclic CGR data for Alloy 690 HAZ vs. Ni-base Welds
Cyclic CGRs are consistent with Alloy 690 (and not the weld) Fatigue and corrosion fatigue data for the alloys of interest (152/52/52M) and in
the orientation of interest would be very useful
10-12
10-11
10-10
10-9
10-8
10-7
10-12 10-11 10-10 10-9 10-8 10-7
CF690-CR-1CF690-CR-3CGR air weld (NUREG-6921)CGR env weld (NUREG-6921)
CG
Ren
v (m
/s)
CGRair (m/s)
Alloy 690 HAZSimulated PWR Water at 320°C
CGR air Ni-weld
CGR env Ni-weld
10-12
10-11
10-10
10-9
10-8
10-7
10-12 10-11 10-10 10-9 10-8 10-7
CF690-CR-1CF690-CR-3CGR air weld (NUREG-6921)CGR env weld (NUREG-6921)
CG
Ren
v (m
/s)
CGRair (m/s)
Alloy 690 HAZAir at 38°C
CGR air Ni-weld
CGR env Ni-weld
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SCC CGRs vs. K for Alloy 690 HAZ
Good agreement between CGRs at constant load (solid) and CGRs determined from cyclic loading
Overall, HAZ CGRs are similar or only slightly higher than those for the as-received alloy Last test: CGR factor 2x higher than that for the alloy in the as-received condition
10-13
10-12
10-11
10-10
10-9
10 15 20 25 30 35 40 45 50
ANL C690-CR-1 (23 cc/kg)ANL C690-LR-2 (23 cc/kg)CF690-CR-1 (A690 HAZ)CF690-CR-3 (A690 HAZ)CF690-CR-4 (A690 HAZ)
Exp
erim
enta
l CG
R (m
/s)
Stress Intensity K (MPa·m1/2)
Alloy 690HAZSimulated PWR environment320°C, 23 cc/kg H2 CGR Curve Alloy 600
75th Percentile
CGR Curve Alloy 60050th Percentile
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Alloy 690 HAZ future tests CRDM Alloy 690 HAZ testing will continue (attractive because cyclic and
SCC data in the base alloys already exists) New Alloy 690 HAZ specimens from the new weld:
combined effect of HAZ (+ banding)
Alloy 690 plate Heat NX3297HK12 (ATI Wah Chang)Alloy 533-Gr B Heat A5401 (Midland reactor lower head)Alloy 152 Heat WC0F6 (Special Metals)
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Alloy 690 HAZ - Summary
The cyclic CGRs of Alloy 690 HAZ appear to shows only slight difference vs. as-received Alloy 690
The SCC CGRs for Alloy 690 HAZ appear to be only slightly higher that those for the as-received condition tested
Fracture mode of Alloy 690 HAZ:- appears to depend on the proximity to the fusion line (1st test)- predominantly TG, with granular appearance (dendritic features – 1st test), TG facets, IG secondary cracks near the fusion line- new approach (fracture surface at an angle vs. fusion line) in progress
Overall, both cyclic and SCC seem to be controlled by Alloy 690 in the as-received condition (TG)