Primary water stress corrosion cracking (PWSCC) of vessel penetrations (VP) fabricated from nickel based alloys such as alloy 600 and alloy 182 weld metal has created a great demand for elucidation of the cracking mechanism and for development of life prediction technologies. The generalized FRI crack growth rate (CGR) formulation was proposed, based on a deformation/oxidation mechanism and a theoretical crack tip strain rate equation derived by the authors. The effects of crack tip oxidation and crack tip mechanics and of their interactions on crack growth can be quantified. Experimental and actual plant data of CGR for alloy 600 in PWR primary water, which are sometimes scattered in CGR-K diagrams, are interpreted with the generalized CGR formulation, emphasizing the effects of temperature, K, yield strength and variations of K with time. It is suggested that it is essential to determine the type of dependency of CGR on K for accurate flaw disposition. The generalized formulation provides a unique parameter for interpreting CGRs as well as a unified method for predicting CGRs within a narrow scattered band even under various testing parameters, which is the basis for accurately predicting component life.

1.
Scott
,
P. M.
, and
Benhamou
,
C.
, 2001, “
An Overview of recent Observations and Interpretations of IGSCC in Nickel Base alloys in PWR Primary Water
,”
Proc. of the 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
, NACE.
2.
Scott
,
P. M.
, and
Combrade
,
P.
, 2003, “
On the Mechanism of Stress Corrosion Crack Initiation and Growth in Alloy 600 Exposed to PWR Primary Water
,”
11th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, Skamania, ANS.
3.
Hong
,
S. L.
,
Boursier
,
J. M.
,
Amzallag
,
C.
, and
Daret
,
J.
, 2001, “
Measurement of Stress Corrosion Growth Rates in Weld Alloy 182 in Primary Water
,”
Proc. of the 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
, NACE.
4.
Bamford
,
W. H.
,
Foster
,
J.
,
Hsu
,
K. R.
,
Tunon-Sanjur
,
L.
, and
McIlree
,
A.
, 2001, “
Alloy 182 Weld Crack Growth, and its Impact on Service-Induced Cracking in Operating PWR Plant Piping
,”
Proc. of the 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, NACE.
5.
Shoji
,
T.
,
Suzuki
,
S.
, and
Ballinger
,
R. G.
, 1995, “
Theoretical Prediction of SCC Growth Behavior
,”
Proc. 7th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, NACE, pp.
881
889
.
6.
Shoji
,
T.
, 2003, “
Progress in the Mechanistic Understanding of BWR SCC and Its Implication to the Prediction of SCC Growth Behavior in Plants
,”
11th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, ANS, Skamania, pp.
588
598
.
7.
Shoji
,
T.
,
Lu
,
Z. P.
, and
Peng
,
Q. J.
, 2003, “
Experimental and Numerical Approaches for Characterizing the Crack Growth Behavior of Alloy 600 in PWR Primary Water, and Life Time Predictions for Welded Structures
,”
Proc. Conf. on Vessel Penetration Inspection, Crack Growth and Repair
, Gaithersburg, MD, U.S. Nuclear Regulatory Commission, pp.
309
336
.
8.
Shoji
,
T.
,
Li
,
G. F.
,
Kwon
,
J. H.
,
Matsushima
,
S.
, and
Lu
,
Z. P.
, 2003, “
Quantification of Yield Strength Effects on IGSCC of Austenitic Stainless Steels in High Temperature Waters
,”
11th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, ANS, Skamania, pp.
834
844
.
9.
Amzallag
,
C.
, and
Vaillant
,
F.
, 1999, “
Stress Corrosion Crack Propagation Rates in Reactor Vessel Head Penetrations in Alloy 600
,”
Proceedings of the 9th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, Newport Beach, CA: TMS, pp.
235
241
.
10.
Materials Reliability Program (MRP)-July, 2002, “Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) of Thick-wall Alloy 600 Material” (MRP-55), By PWR Materials Reliability Program Alloy 600 Issues Task Group.
11.
Amzallag
,
C.
,
Boursier
,
J. M.
,
Pages
,
C.
, and
Gimond
,
C.
, 2001, “
Stress Corrosion Life Assessment of 182 and 82 Welds Used in PWR Components
,”
Proc. of the 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, NACE.
12.
Magdowski
,
R.
,
Vaillant
,
F.
,
Amzallag
,
C.
, and
Speidel
,
M. O.
, 1997, “
Stress Corrosion Crack Growth Rates of Alloy 600 in Simulated PWR Coolant
,”
Proc. of the 8th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
,
S. M.
Bruemmer
, ed.,
American Nuclear Society
, La Grange Park, IL, pp.
333
338
.
13.
Amzallag
,
C.
,
Hong
,
S. Le
,
Page
,
C.
, and
Gelpi
,
A.
, 1999, “
Stress corrosion life assessment of alloy 600 components
,”
Proceedings of the 9th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, Newport Beach, CA: TMS, pp.
243
250
.
14.
Foster
,
J. P.
,
Bamford
,
W. H.
,
Pathania
,
R. S.
, and
McIlree
,
A.
, 2001, “
Effects of Loading on Alloy 600 Crack Growth Rate Behavior
,”
Proc. 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, NACE.
15.
Foster
,
J. P.
,
Bamford
,
W. H.
, and
Pathania
,
R. S.
, 2003, “
Alloy 600 Crack Growth Rate Stress Intensity Dependence
,”
11th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Skamania
, ANS. pp.
156
165
.
16.
Speidel
,
M. O.
, and
Magdowski
,
R.
, 2000, “
Stress Corrosion Crack Growth in Alloy 600 Exposed to PWR and BWR Environments
,” Corrosion/2000, NACE, TX, Paper No.222.
17.
Moshier
,
W. C.
, and
Brown
,
C. M.
, 2000, “
Effects of Cold Work and Processing Orientation on Stress Corrosion Cracking Behavior of Alloy 600
,”
Corrosion (Houston)
0010-9312,
56
(
3
), pp.
307
320
.
18.
Cassagne
,
T.
,
Caron
,
D.
,
Daret
,
J.
, and
Lefevre
,
Y.
, 1999, “
Stress Corrosion Crack Growth Measurements in Alloys 600 and 182
,”
Proceedings of the 9th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, Newport Beach, CA: TMS, pp.
217
224
.
19.
Amzallag
,
C.
,
Boursier
,
J. M.
,
Pages
,
C.
, and
Gimond
,
C.
, 2002, “
Stress Corrosion Life Experience of 182 and 82 Welds in French PWR’s
,” Fontevraud V, Fontevraud, French Nuclear Energy Society, Paper No. 026, CDROM.
20.
Ford
,
F. P.
, 1996, “
Quantitative Prediction of Environmentally Assisted Cracking
,”
Corrosion (Houston)
0010-9312,
52
(
5
), pp.
375
395
.
21.
Birks
,
N.
, and
Meier
,
G. H.
, 1983,
Introduction to High Temperature Oxidation of Metals
,
Edward Arnold Ltd
,
London
, p.
42
.
22.
Badini
,
C.
, and
Laurella
,
F.
, 2001, “
Oxidation of FeCrAl alloy: Influence of Temperature and Atmosphere on Scale Growth Rate and Mechanism
,”
Surf. Coat. Technol.
0257-8972,
135
, pp.
291
298
.
23.
Heusler
,
K. E.
, 1997, “
Fundamental Aspects of the Corrosion of Alloys
,”
Corros. Sci.
0010-938X,
39
(
7
), pp.
1177
1191
.
24.
Gao
,
Y. C.
, and
Kwang
,
K. C.
, 1981, “
Elastic-Plastic Fields in Steady Crack Growth in a Strain-Hardening Material
,” 5th International Conference on Fracture, France,
2
, pp.
669
682
.
25.
Gerberich
,
W. W.
,
Davidson
,
D. L.
, and
Kaczorowski
,
M.
, 1990, “
Experimental and Theoretical Strain Distributions for Stationary and Growing Cracks
,”
J. Mech. Phys. Solids
0022-5096,
38
(
1
), pp.
87
113
.
26.
Champigny
,
F.
,
Chapelier
,
F.
,
Amzallag
,
C.
, and
Vaillant
,
F.
, 2003, “
Maintenance Strategy of Inconel Components in PWR Primary System in France
,”
Proc. Conf. on Vessel Penetration Inspection, Crack Growth and Repair
. Gaithersburg, MD, U.S. Nuclear Regulatory Commission, pp.
85
94
.
You do not currently have access to this content.