The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) provides rules for the design of Class 1 components of nuclear power plants. However, the Code design curves do not address the effects of light water reactor (LWR) water environments. Existing fatigue strain-versus-life (ε–N) data illustrate significant effects of LWR water environments on the fatigue resistance of pressure vessel and piping steels. Extensive studies have been conducted at Argonne National Laboratory (Argonne) and elsewhere to investigate the effects of LWR environments on the fatigue life. This article summarizes the results of these studies. The existing fatigue ε–N data were evaluated to identify the various material, environmental, and loading conditions that influence the fatigue crack initiation; a methodology for estimating fatigue lives as a function of these parameters was developed. The effects were incorporated into the ASME Code Section III fatigue evaluations in terms of an environmental correction factor, Fen, which is the ratio of fatigue life in air at room temperature to the life in the LWR water environment at reactor operating temperatures. Available fatigue data were used to develop fatigue design curves for carbon and low-alloy steels, austenitic stainless steels (SSs), and nickel–chromium–iron (Ni–Cr–Fe) alloys and their weld metals. A review of the Code Section III fatigue adjustment factors of 2 and 20 is also presented, and the possible conservatism inherent in the choice is evaluated. A brief description of potential effects of neutron irradiation on fatigue crack initiation is presented.

Issue Section:
Review Article
Keywords:
Fatigue, Fracture prediction
Topics:
Alloys, Fatigue, Fatigue life, Steel, Fatigue design, Water, Carbon, Temperature, Light water reactors, Stress

References

1.
Hale
,
D. A.
,
Wilson
,
S. A.
,
Kiss
,
E.
, and
Giannuzzi
,
A. J.
,
1977
, “
Low-Cycle Fatigue Evaluation of Primary Piping Materials in a BWR Environment
,” U.S. Nuclear Regulatory Commission, Washington, DC, Report No. GEAP-20244.
2.
Hale
,
D. A.
,
Wilson
,
S. A.
,
Kass
,
J. N.
, and
Kiss
,
E.
,
1981
, “
Low Cycle Fatigue Behavior of Commercial Piping Materials in a BWR Environment
,”
J. Eng. Mater. Technol.
,
103
(
1
), pp.
15
–
25
.
Google Scholar
Crossref
Search ADS
 
3.
Ranganath
,
S.
,
Kass
,
J. N.
, and
Heald
,
J. D.
,
1982
, “
Fatigue Behavior of Carbon Steel Components in High-Temperature Water Environments
,” BWR Environmental Cracking Margins for Carbon Steel Piping, Electric Power Research Institute, Palo Alto, CA, Report No. EPRI NP-2406, Appendix 3.
4.
Ranganath
,
S.
,
Kass
,
J. N.
, and
Heald
,
J. D.
,
1982
, “
Fatigue Behavior of Carbon Steel Components in High-Temperature Water Environments
,”
Low-Cycle Fatigue and Life Prediction
,
C.
Amzallag
,
B. N.
Leis
,
P.
Rabbe
, eds.,
American Society for Testing and Materials
,
Philadelphia, PA
, pp.
436
–
459
, Paper No. ASTM STP 770.
5.
JNES-SS Report
,
2011
, “
Environmental Fatigue Evaluation Method for Nuclear Power Plants
,” Nuclear Energy System Safety Division, Japan Nuclear Energy Safety Organization, Tokyo, Japan,
Report No. JNES-SS-1005
.
6.
Higuchi
,
M.
, and
Iida
,
K.
,
1991
, “
Fatigue Strength Correction Factors for Carbon and Low-Alloy Steels in Oxygen-Containing High-Temperature Water
,”
Nucl. Eng. Des.
,
129
(
3
), pp.
293
–
306
.
Google Scholar
Crossref
Search ADS
 
7.
Higuchi
,
M.
,
1992
, private communication, Ishikawajima-Harima Heavy Industries, Japan, to M. Prager of the Pressure Vessel Research Council.
8.
Kanasaki
,
H.
,
Hayashi
,
M.
,
Iida
,
K.
, and
Asada
,
Y.
,
1995
, “
Effects of Temperature Change on Fatigue Life of Carbon Steel in High Temperature Water
,”
Fatigue and Crack Growth: Environmental Effects, Modeling Studies, and Design Considerations
, Vol.
306
,
S.
Yukawa
, ed.,
American Society of Mechanical Engineers
,
New York
, pp.
117
–
122
.
9.
Nakao
,
G.
,
Kanasaki
,
H.
,
Higuchi
,
M.
,
Iida
,
K.
, and
Asada
,
Y.
,
1995
, “
Effects of Temperature and Dissolved Oxygen Content on Fatigue Life of Carbon and Low–Alloy Steels in LWR Water Environment
,”
Fatigue and Crack Growth: Environmental Effects, Modeling Studies, and Design Considerations
, Vol.
306
,
S.
Yukawa
, ed.,
American Society of Mechanical Engineers
,
New York
, pp.
123
–
128
.
10.
Higuchi
,
M.
,
Iida
,
K.
, and
Sakaguchi
,
K.
,
2001
, “
Effects of Strain Rate Fluctuation and Strain Holding on Fatigue Life Reduction for LWR Structural Steels in Simulated PWR Water
,”
Pressure Vessel and Piping Codes and Standards
, Vol.
419
,
M. D.
Rana
, ed.,
American Society of Mechanical Engineers
,
New York
, pp.
143
–
152
.
11.
Hirano
,
A.
,
Yamamoto
,
M.
,
Sakaguchi
,
K.
,
Shoji
,
T.
, and
Iida
,
K.
,
2002
, “
Effects of Water Flow Rate on Fatigue Life of Ferritic and Austenitic Steels in Simulated LWR Environment
,”
Pressure Vessel and Piping Codes and Standards
, Vol.
439
,
M. D.
Rana
, ed.,
American Society of Mechanical Engineers
,
New York
, pp.
143
–
150
.
12.
Hirano
,
A.
,
Yamamoto
,
M.
,
Sakaguchi
,
K.
, and
Shoji
,
T.
,
2004
, “
Effects of Water Flow Rate on Fatigue Life of Carbon and Stainless Steels in Simulated LWR Environment
,”
Pressure Vessel and Piping Codes and Standards
, Vol.
480
,
American Society of Mechanical Engineers
,
New York
, pp.
109
–
119
.
13.
Kanasaki
,
H.
,
Umehara
,
R.
,
Mizuta
,
H.
, and
Suyama
,
T.
,
1997
, “
Fatigue Lives of Stainless Steels in PWR Primary Water
,”
14th International Conference on Structural Mechanics in Reactor Technology
(
SMiRT 14
), Lyon, France, Aug. 17–22, pp.
473
–
483
.
14.
Kanasaki
,
H.
,
Umehara
,
R.
,
Mizuta
,
H.
, and
Suyama
,
T.
,
1997
, “
Effects of Strain Rate and Temperature Change on the Fatigue Life of Stainless Steel in PWR Primary Water
,”
14th International Conference on Structural Mechanics in Reactor Technology
(
SMiRT 14
), Lyon, France, Aug. 17–22, pp.
485
–
493
.
15.
Higuchi
,
M.
, and
Iida
,
K.
,
1997
, “
Reduction in Low–Cycle Fatigue Life of Austenitic Stainless Steels in High–Temperature Water
,”
Pressure Vessel and Piping Codes and Standards
, Vol.
353
,
D. P.
Jones
,
B. R.
Newton
,
W. J.
O'Donnell
,
R.
Vecchio
,
G. A.
Antaki
,
D.
Bhavani
,
N. G.
Cofie
, and
G. L.
Hollinger
, eds.,
American Society of Mechanical Engineers
,
New York
, pp.
79
–
86
.
16.
Hayashi
,
M.
,
1998
, “
Thermal Fatigue Strength of Type 304 Stainless Steel in Simulated BWR Environment
,”
Nucl. Eng. Des.
,
184
(
1
), pp.
135
–
144
.
Google Scholar
Crossref
Search ADS
 
17.
Tsutsumi
,
K.
,
Kanasaki
,
T.
,
Umakoshi
,
H.
,
Nakamura
,
T.
,
Urata
,
S.
,
Mizuta
,
H.
, and
Nomoto
,
S.
,
2000
, “
Fatigue Life Reduction in PWR Water Environment for Stainless Steels
,”
Assessment Methodologies for Preventing Failure: Service Experience and Environmental Considerations
, Vol.
410–412
,
R.
Mohan
, ed.,
American Society of Mechanical Engineers
,
New York
, pp.
23
–
34
.
18.
Tsutsumi
,
K.
,
Dodo
,
T.
,
Kanasaki
,
H.
,
Nomoto
,
S.
,
Minami
,
Y.
, and
Nakamura
,
T.
,
2001
, “
Fatigue Behavior of Stainless Steel Under Conditions of Changing Strain Rate in PWR Primary Water
,”
Pressure Vessel and Piping Codes and Standards
, Vol.
419
,
M. D.
Rana
, ed.,
American Society of Mechanical Engineers
,
New York
, pp.
135
–
141
.
19.
Tsutsumi
,
K.
,
Higuchi
,
M.
,
Iida
,
K.
, and
Yamamoto
,
Y.
,
2002
, “
The Modified Rate Approach to Evaluate Fatigue Life Under Synchronously Changing Temperature and Strain Rate in Elevated Temperature Water
,”
Pressure Vessel and Piping Codes and Standards
, Vol.
439
,
M. D.
Rana
, ed.,
American Society of Mechanical Engineers
,
New York
, pp.
99
–
107
.
20.
Nomura
,
Y.
,
Higuchi
,
M.
,
Asada
,
Y.
, and
Sakaguchi
,
K.
,
2004
, “
The Modified Rate Approach Method to Evaluate Fatigue Life Under Synchronously Changing Temperature and Strain Rate in Elevated Temperature Water in Austenitic Stainless Steels
,”
Pressure Vessel and Piping Codes and Standards
, Vol.
480
,
American Society of Mechanical Engineers
,
New York
, pp.
99
–
108
.
21.
Higuchi
,
M.
,
Sakaguchi
,
K.
,
Hirano
,
A.
, and
Nomura
,
Y.
,
2006
, “
Revised and New Proposal of Environmental Fatigue Life Correction Factor (Fen) for Carbon and Low-Alloy Steels and Nickel Alloys in LWR Water Environments
,”
ASME
Paper No. PVP2006-ICPVT-93194.
22.
Chopra
,
O. K.
, and
Shack
,
W. J.
,
1998
, “
Effects of LWR Coolant Environments on Fatigue Design Curves of Carbon and Low-Alloy Steels
,”
Report No. NUREG/CR-6583, ANL-97/18
.
23.
Gavenda
,
D. J.
,
Luebbers
,
P. R.
, and
Chopra
,
O. K.
,
1997
, “
Crack Initiation and Crack Growth Behavior of Carbon and Low-Alloy Steels
,”
Fatigue and Fracture 1
, Vol.
350
,
S.
Rahman
,
K. K.
Yoon
,
S.
Bhandari
,
R.
Warke
, and
J. M.
Bloom
, eds.,
American Society of Mechanical Engineers
,
New York
, pp.
243
–
255
.
24.
Chopra
,
O. K.
, and
Shack
,
W. J.
,
2001
, “
Environmental Effects on Fatigue Crack Initiation in Piping and Pressure Vessel Steels
,”
Report No. NUREG/CR-6717, ANL-00/27
.
25.
Chopra
,
O. K.
, and
Shack
,
W. J.
,
1997
, “
Evaluation of Effects of LWR Coolant Environments on Fatigue Life of Carbon and Low-Alloy Steels
,”
Effects of the Environment on the Initiation of Crack Growth
,
W. A.
Van Der Sluys
,
R. S.
Piascik
, and
R.
Zawierucha
, eds.,
American Society for Testing and Materials
,
Philadelphia, PA
, pp.
247
–
266
, Paper No. ASTM STP 1298.
26.
Chopra
,
O. K.
, and
Gavenda
,
D. J.
,
1998
, “
Effects of LWR Coolant Environments on Fatigue Lives of Austenitic Stainless Steels
,”
ASME J. Pressure Vessel Technol.
,
120
(
2
), pp.
116
–
121
.
Google Scholar
Crossref
Search ADS
 
27.
Smith
,
J. L.
, and
Chopra
,
O. K.
,
1999
, “
Crack Initiation in Smooth Fatigue Specimens of Austenitic Stainless Steel in Light Water Reactor Environments
,”
Operations, Applications, and Components
, Vol.
395
,
I. T.
Kisisel
, ed.,
American Society of Mechanical Engineers
,
New York
, pp.
235
–
242
.
28.
Chopra
,
O. K.
,
1999
, “
Effects of LWR Coolant Environments on Fatigue Design Curves of Austenitic Stainless Steels
,”
Report No. NUREG/CR-5704, ANL-98/31
.
29.
Chopra
,
O. K.
,
2002
, “
Mechanism and Estimation of Fatigue Crack Initiation in Austenitic Stainless Steels in LWR Environments
,”
Report No. NUREG/CR-6787, ANL-01/25
.
30.
Chopra
,
O. K.
, and
Shack
,
W. J.
,
2003
, “
Review of the Margins for ASME Code Design Curves–Effects of Surface Roughness and Material Variability
,”
Report No. NUREG/CR-6815, ANL-02/39
.
31.
Chopra
,
O. K.
,
Alexandreanu
,
B.
, and
Shack
,
W. J.
,
2005
, “
Effect of Material Heat Treatment on Fatigue Crack Initiation in Austenitic Stainless Steels in LWR Environments
,”
Report No. NUREG/CR-6878, ANL03/35
.
32.
Chopra
,
O. K.
, and
Shack
,
W. J.
,
2007
, “
Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials
,”
Report No. NUREG/CR-6909, ANL-06/08
.
33.
Terrell
,
J. B.
,
1988
, “
Fatigue Life Characterization of Smooth and Notched Piping Steel Specimens in 288 °C Air Environments
,” Materials Engineering Associates, Inc., Lanham, MD, Report No. NUREG/CR-5013, EM-2232.
34.
Terrell
,
J. B.
,
1988
, “
Fatigue Strength of Smooth and Notched Specimens of ASME SA 106–B Steel in PWR Environments
,” Materials Engineering Associates, Inc., Lanham, MD, Report No. NUREG/CR-136, MEA-2289.
35.
Lenz
,
E.
,
Wieling
,
N.
, and
Muenster
,
H.
,
1988
, “
Influence of Variation of Flow Rates and Temperature on the Cyclic Crack Growth Rate Under BWR Conditions
,”
Environmental Degradation of Materials in Nuclear Power Systems–Water Reactors
,
The Metallurgical Society
,
Warrendale, PA
.
36.
Garud
,
Y. S.
,
Paterson
,
S. R.
,
Dooley
,
R. B.
,
Pathania
,
R. S.
,
Hickling
,
J.
, and
Bursik
,
A.
,
1997
, “
Corrosion Fatigue of Water Touched Pressure Retaining Components in Power Plants
,” Final Report, Electric Power Research Institute, Palo Alto, CA, Report No. EPRI TR-106696.
37.
O'Donnell
,
W. J.
, and
O'Donnell
,
W. J.
,
2008
, “
Temperature Dependence of Reactor Water Environmental Fatigue Effects on Carbon, Low-Alloy and Austenitic Stainless Steels
,”
ASME
Paper No. PVP2008-61917.
38.
Nomura
,
Y.
,
Asada
,
S.
,
Nakamura
,
T.
, and
Tanaka
,
M.
,
2010
, “
Effects of Continuous Strain Rate Changing on Environmental Fatigue for Stainless Steels in PWR Environment
,”
ASME
Paper No. PVP2010-25194.
39.
Le Duff
,
J. A.
,
Lefrancois
,
A.
,
Vernot
,
J. P.
, and
Bossu
,
D.
,
2010
, “
Effect of Loading Signal Shape and of Surface Finish on the Low Cycle Fatigue Behavior of 304L Stainless Steel in PWR Environment
,”
ASME
Paper No. PVP2010-26027.
40.
Amzallag
,
C.
,
Rabbe
,
P.
,
Gallet
,
G.
, and
Lieurade
,
H.-P.
,
1978
, “
Influence des Conditions de Sollicitation Sur le Comportement en Fatigue Oligocyclique D'aciers Inoxydables Austénitiques
,” Memoires Scientifiques Revue Metallurgie Mars, pp.
161
–
173
.
41.
Solomon
,
H. D.
,
Amzallag
,
C.
,
Vallee
,
A. J.
, and
De Lair
,
R. E.
,
2005
, “
Influence of Mean Stress on the Fatigue Behavior of 304L SS in Air and PWR Water
,”
ASME
Paper No. PVP2005-71064.
42.
Solomon
,
H. D.
,
Amzallag
,
C.
,
De Lair
,
R. E.
, and
Vallee
,
A. J.
,
2005
, “
Comparison of the Fatigue Life of Type 304L SS as Measured in Load and Strain Controlled Tests
,” Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Plants–Water Reactors,
T. R.
Allen
,
P. J.
King
, and
L.
Nelson
, eds.,
The Minerals, Metals and Materials Society
, Warrendale, PA, pp. 1101–1110.
43.
Solomon
,
H. D.
,
Amzallag
,
C.
,
De Lair
,
R. E.
, and
Vallee
,
A. J.
,
2004
, “
Strain Controlled Fatigue of Type 304L SS in Air and PWR Water
,”
Third International Conference on Fatigue of Reactor Components
, Seville, Spain, Oct. 3–6, pp. 1–23.
44.
Jaske
,
C. E.
, and
O'Donnell
,
W. J.
,
1977
, “
Fatigue Design Criteria for Pressure Vessel Alloys
,”
ASME J. Pressure Vessel Technol.
,
99
(
4
), pp.
584
–
592
.
Google Scholar
Crossref
Search ADS
 
45.
Conway
,
J. B.
,
Stent
,
R. H.
, and
Berling
,
T.
,
1975
, “
Fatigue, Tensile, and Relaxation Behavior of Stainless Steels
,” U.S. Atomic Energy Commission, Washington, DC, Report No. TID-26135.
46.
Keller
,
D. L.
,
1977
, “
Progress on LMFBR Cladding, Structural, and Component Materials Studies During July, 1971 Through June, 1972
,” Final Report, Task 32, Battelle–Columbus Laboratories, Columbus, OH, Report No. BMI-
1928
.
47.
Smith
,
R. W.
,
Hirschberg
,
M. H.
, and
Manson
,
S. S.
,
1963
, “
Fatigue Behavior of Materials Under Strain Cycling in Low and Intermediate Life Range
,” Lewis Research Center, Cleveland, OH, Report No. NASA TN D-1574.
48.
Krempl
,
E.
,
1966
, “
Low Cycle Fatigue Crack Initiation in the Presence of Stress/Strain Concentration
,” Reactor Primary Coolant System Rupture Study, Quarterly Progress Report No. 3, General Electric, San Jose, CA, pp.
6:6
–
6:23
.
49.
Jacko
,
R. J.
,
1983
, “
Fatigue Performance of Ni–Cr–Fe Alloy 600 Under Typical PWR Steam Generator Conditions
,” Electric Power Research Institute, Palo Alto, CA,
Report No. EPRI NP-2957
.
50.
Dinerman
,
A. E.
,
1960
, “
Cyclic Strain Fatigue of Inconel at 75 to 600°F
,” Knolls Atomic Power Laboratory, Schenectady, NY, Report No. KAPL-2084.
51.
Mowbray
,
D. F.
,
Sokol
,
G. J.
, and
Savidge
,
R. E.
,
1965
, “
Fatigue Characteristics of Ni–Cr–Fe Alloys With Emphasis on Pressure-Vessel Cladding
,” Knolls Atomic Power Laboratory, Schenectady, NY, Report No. KAPL-3108.
52.
Jaske
,
C. E.
,
Mindlin
,
H.
, and
Perrin
,
J. S.
,
1972
, “
Low-Cycle Fatigue of Incoloy Alloy 800
,” Battelle's Columbus Laboratories, Columbus, OH, Topical Report No. BMI-1921.
53.
McGowan
,
E. J.
, and
Faber
,
J. W.
,
1969
, “
Effects of Electric Discharge and Electrochemical Machining on the Fatigue Strength of Selected Structural Materials
,” Bettis Atomic Power Laboratory, West Mifflin, PA, Report No. WAPD-TM-787.
54.
Conway
,
J. B.
,
1969
, “
Short Term Tensile and Low-Cycle Fatigue Studies of Incoloy 800
,” General Electric Company, San Jose, CA, Report No. GEMP-732.
55.
Nachtigall
,
A. J.
,
1974
, “
Strain Cycling Fatigue Behavior of Ten Structural Metals Tested in Liquid Helium (4K), in Liquid Nitrogen (78K), and in Ambient Air (300K)
,” Lewis Research Center, Cleveland, OH, Report No. NASA TN D-7532.
56.
Brinkman
,
C. R.
, and
Korth
,
G. E.
,
1974
, “
Strain Fatigue and Tensile Behavior of Inconel 718 From Room Temperature to 650 °C
,”
J. Test. Eval.
,
2
(
4
), pp.
249
–
259
.
Google Scholar
Crossref
Search ADS
 
57.
Van Der Sluys
,
W. A.
,
Young
,
B. A.
, and
Doyle
,
D.
,
2000
, “
Corrosion Fatigue Properties on Alloy 690 and Some Nickel-Based Weld Metals
,” Assessment Methodologies for Preventing Failure: Service Experience and Environmental Considerations, Vol.
410–412
, R. Mohan, ed., American Society of Mechanical Engineers, New York, pp.
85
–
91
.
58.
Chopra
,
O.
, and
Stevens
,
G. L.
,
2016
, “
Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials
,”
Report No. NUREG/CR-6909 Rev. 1 ANL-12/60
.
59.
ASTM
,
2009
, “
Standard Terminology Relating to Fatigue and Fracture Testing
,” American Society for Testing and Materials, Philadelphia, PA,
Standard No. E1823-13
.
60.
ASTM
,
2005
, “
Standard Practice for Strain-Controlled Fatigue Testing
,” American Society for Testing and Materials, Philadelphia, PA,
Standard No. E606-04
.
61.
Langer
,
B. F.
,
1962
, “
Design of Pressure Vessels for Low-Cycle Fatigue
,”
ASME J. Basic Eng.
,
84
(
3
), pp.
389
–
402
.
Google Scholar
Crossref
Search ADS
 
62.
ASME
,
1969
,
Criteria of the ASME Boiler and Pressure Vessel Code for Design by Analysis in Sections III and VIII, Division 2
,
The American Society of Mechanical Engineers
,
New York
.
63.
Cooper
,
W. E.
,
1992
, “
The Initial Scope and Intent of the Section III Fatigue Design Procedure
,”
Workshop on Cyclic Life and Environmental Effects in Nuclear Applications
, Welding Research Council, Clearwater, FL, Jan. 21–22.
64.
ASTM
,
2006
, “
Standard Practice for Statistical Analysis of Linear or Linearized Stress-Life (S-N) and Strain-Life (ε–N) Fatigue Data
,” American Society for Testing and Materials, Philadelphia, PA,
Standard No. E739-91
.
65.
Keisler
,
J.
,
Chopra
,
O. K.
, and
Shack
,
W. J.
,
1995
, “
Fatigue Strain-Life Behavior of Carbon and Low-Alloy Steels, Austenitic Stainless Steels, and Alloy 600 in LWR Environments
,”
Report No. NUREG/CR-6335, ANL–95/15
.
66.
Johnson
,
L. G.
,
1951
, “
The Median Ranks of Sample Values in Their Population With an Application to Certain Fatigue Studies
,”
Ind. Math.
,
2
, pp.
1
–
9
.
67.
Lipson
,
C.
, and
Sheth
,
N. J.
,
1973
,
Statistical Design and Analysis of Engineering Experiments
,
McGraw-Hill
,
New York
.
68.
Beck
,
J.
, and
Arnold
,
K.
,
1977
,
Parameter Estimation in Engineering and Science
,
Wiley
,
New York
.
69.
Abdel–Raouf
,
H.
,
Plumtree
,
A.
, and
Topper
,
T. H.
,
1973
, “
Effects of Temperature and Deformation Rate on Cyclic Strength and Fracture of Low–Carbon Steel
,”
Cyclic Stress–Strain Behavior–Analysis, Experimentation, and Failure Prediction
, American Society for Testing and Materials, Philadelphia, PA, pp.
28
–
57
, Paper No. ASTM STP 519.
70.
Lee
,
B. H.
, and
Kim
,
I. S.
,
1995
, “
Dynamic Strain Aging in the High–Temperature Low–Cycle Fatigue of SA 508 Cl. 3 Forging Steel
,”
J. Nucl. Mater.
,
226
(1–2), pp.
216
–
225
.
Google Scholar
Crossref
Search ADS
 
71.
Kooistra
,
L. F.
,
Lange
,
E. A.
, and
Pickett
,
A. G.
,
1964
, “
Full-Size Pressure Vessel Testing and Its Application to Design
,”
J. Eng. Power
,
86
(
4
), pp.
419
–
428
.
Google Scholar
Crossref
Search ADS
 
72.
Stout
,
K. J.
,
1981
, “
Surface Roughness–Measurement, Interpretation, and Significance of Data
,”
Mat. & Des.
,
2
(6), pp.
287
–
295
.
Google Scholar
Crossref
Search ADS
 
73.
Maiya
,
P. S.
, and
Busch
,
D. E.
,
1975
, “
Effect of Surface Roughness on Low–Cycle Fatigue Behavior of Type 304 Stainless Steel
,”
Metall. Trans. A
,
6
(
9
), pp.
1761
–
1766
.
Google Scholar
Crossref
Search ADS
 
74.
Maiya
,
P. S.
,
1975
, “
Effect of Surface Roughness and Strain Range on Low–Cycle Fatigue Behavior of Type 304 Stainless Steel
,”
Scr. Metall.
,
9
(
11
), pp.
1277
–
1282
.
Google Scholar
Crossref
Search ADS
 
75.
Iida
,
K.
,
1989
, “
A Study of Surface Finish Effect Factor in ASME B & PV Code Section III
,”
Pressure Vessel Technology
, Vol.
2
,
L.
Cengdian
, and
R. W.
Nichols
, eds.,
Pergamum Press
,
New York
, pp.
727
–
734
.
76.
Le Duff
,
J. A.
,
Lefrancois
,
A.
, and
Vernot
,
J. P.
,
2008
, “
Effect of Surface Finish and Loading Conditions on the Low Cycle Fatigue Behavior of Austenitic Stainless Steel in PWR Environment Comparison of LCF Test Results With NUREG/CR-6909 Life Estimates
,”
ASME
Paper No. PVP2008-61894.
77.
Le Duff
,
J. A.
,
Lefrancois
,
A.
, and
Vernot
,
J. P.
,
2009
, “
Effect of Surface Finish and Loading Conditions on the Low Cycle Fatigue Behavior of Austenitic Stainless Steel in PWR Environment for Various Strain Amplitude Levels
,”
ASME
Paper No. PVP2009-78129.
78.
Pompetzki
,
M. A.
,
Topper
,
T. H.
, and
DuQuesnay
,
D. L.
,
1990
, “
The Effect of Compressive Under Loads and Tensile Overloads on Fatigue Damage Accumulation in SAE 1045 Steel
,”
Int. J. Fatigue
,
12
(
3
), pp.
207
–
213
.
Google Scholar
Crossref
Search ADS
 
79.
Conle
,
A.
, and
Topper
,
T. H.
,
1980
, “
Overstrain Effects During Variable Amplitude Service History Testing
,”
Int. J. Fatigue
,
2
(
3
), pp.
130
–
136
.
Google Scholar
Crossref
Search ADS
 
80.
Nian
,
L.
, and
Bai-Ping
,
D.
,
1992
, “
Effect of Monotonic and Cyclic Prestrain on the Fatigue Threshold in Medium-Carbon Steels
,”
Int. J. Fatigue
,
14
(
1
), pp.
41
–
44
.
Google Scholar
Crossref
Search ADS
 
81.
Manjoine
,
M. J.
,
1981
, “
Fatigue Damage Models for Annealed Type 304 Stainless Steel Under Complex Strain Histories
,”
6th International Conference on Structural Mechanics in Reactor Technology (SMiRT)
, North-Holland Publishing, Amsterdam, The Netherlands, pp.
1
–
13
.
82.
Nian
,
L.
, and
Bai-Ping
,
D.
,
1995
, “
The Effect of Low–Stress High–Cycle Fatigue on the Microstructure and Fatigue Threshold of a 40Cr Steel
,”
Int. J. Fatigue
,
17
(
1
), pp.
43
–
48
.
Google Scholar
Crossref
Search ADS
 
83.
Solin
,
J. P.
,
Reese
,
S.
, and
Mayinger
,
W.
,
2011
, “
Discussion on Fatigue Design Curves for Stainless Steels
,”
ASME
Paper No. PVP2011-57943.
84.
Solin
,
J. P.
,
2006
, “
Fatigue of Stabilized SS and 316NG Alloy in PWR Environment
,”
ASME
Paper No. PVP2006-ICPVT-93833.
85.
Stambaugh
,
K. A.
,
Leeson
,
D. H.
,
Lawrence
,
F. V.
,
Hou
,
C. Y.
, and
Banas
,
G.
,
1995
, “
Reduction of S-N Curves for Ship Structural Details
,”
WRC Bulletin No. 398
.
86.
Manjoine
,
M. J.
, and
Johnson
,
R. L.
,
1994
, “
Analysis of Fatigue Data for Evaluation of Fatigue Life at Temperatures Below the Creep Range
,”
Material Durability/Life Prediction Modeling: Materials for the 21st Century
, Vol.
290
,
American Society of Mechanical Engineers
,
New York
, pp. 1–6.
87.
Miller
,
K. J.
, and
O'Donnell
,
W. J.
,
1999
, “
The Fatigue Limit and Its Elimination
,”
Fatigue Fract. Eng. Mater. Struct.
,
22
(
7
), pp.
545
–
557
.
Google Scholar
Crossref
Search ADS
 
88.
Shahinian
,
P.
,
Watson
,
H. E.
, and
Smith
,
H. H.
,
1972
, “
Effect of Neutron Irradiation on Fatigue Crack Propagation in Types 304 and 316 Stainless Steels at High Temperature
,” Naval Research Laboratory, Washington, DC, NRL Report No. 7446.
89.
James
,
L. A.
, and
Knecht
,
R. L.
,
1973
, “
Fatigue-Crack Propagation in Fast-Neutron-Irradiated Types-304 and -316 Stainless Steels
,”
Nucl. Technol.
,
19
(3), pp.
148
–
155
.
Google Scholar
Crossref
Search ADS
 
90.
James
,
L. A.
,
1975
, “
The Effect of Fast Neutron Irradiation Upon the Fatigue-Crack Propagation Behavior of Two Austenitic Stainless Steels
,”
J. Nucl. Mater.
,
59
(2), pp.
183
–
191
.
Google Scholar
Crossref
Search ADS
 
91.
Michel
,
D. J.
,
1977
, “
Irradiation Effects on Fatigue Crack Propagation in Austenitic Stainless Steels
,” Naval Research Laboratory, Washington, DC, NRL Memorandum Report No. 3610.
92.
Michel
,
D. J.
, and
Smith
,
H. H.
,
1977
, “
Fatigue Crack Propagation in Neutron Irradiated Type 304 and Type 308 Stainless Steel Plate and Weld Materials
,”
J. Nucl. Mater.
,
71
(
1
), pp.
173
–
177
.
Google Scholar
Crossref
Search ADS
 
93.
Shahinian
,
P.
,
Watson
,
H. E.
, and
Smith
,
H. H.
,
1972
, “
Neutron Irradiation Effects on Fatigue Crack Growth in Types 304 and 316 Stainless Steels
,” Naval Research Laboratory, Washington, DC, NRL Memorandum Report No. 2505.
94.
Fyfitch
,
S.
,
Xu
,
H.
,
Moore
,
K.
, and
Gurdal
,
R.
,
2005
, “
PWR Internals Materials Aging Degradation Mechanism Screening and Threshold Values (MRP-175)
,” Materials Reliability Program, Electric Power Research Institute, Palo Alto, CA,
Report No. EPRI 1012081
.
95.
Van Der Sluys
,
W. A.
,
2003
, “
PVRC's Position on Environmental Effects on Fatigue Life in LWR Applications
,” Welding Research Council, New York,
WRC Bulletin No. 487
.
96.
Iida
,
K.
,
Bannai
,
T.
,
Higuchi
,
M.
,
Tsutsumi
,
K.
, and
Sakaguchi
,
K.
,
2001
, “
Comparison of Japanese MITI Guideline and Other Methods for Evaluation of Environmental Fatigue Life Reduction
,” Pressure Vessel and Piping Codes and Standards, Vol.
419
,
M. D.
Rana
, ed.,
American Society of Mechanical Engineers
,
New York
, pp.
73
–
81
.
97.
Chopra
,
O. K.
, and
Shack
,
W. J.
,
1999
, “
Overview of Fatigue Crack Initiation in Carbon and Low-Alloy Steels in Light Water Reactor Environments
,”
ASME J. Pressure Vessel Technol.
,
121
(
1
), pp.
49
–
60
.
Google Scholar
Crossref
Search ADS
 
98.
Higuchi
,
M.
,
2000
, “
Revised Proposal of Fatigue Life Correction Factor Fen for Carbon and Low Alloy Steels in LWR Water Environments
,”
Assessment Methodologies for Preventing Failure: Service Experience and Environmental Considerations
, Vol.
410–412
,
R.
Mohan
, ed.,
American Society of Mechanical Engineers
,
New York
, pp.
35
–
44
.
99.
Mehta
,
H. S.
, and
Gosselin
,
S. R.
,
1998
, “
Environmental Factor Approach to Account for Water Effects in Pressure Vessel and Piping Fatigue Evaluations
,”
Nucl. Eng. Des.
,
181
(1–3), pp.
175
–
197
.
Google Scholar
Crossref
Search ADS
 
100.
Mehta
,
H. S.
,
2000
, “
An Update on the Consideration of Reactor Water Effects in Code Fatigue Initiation Evaluations for Pressure Vessels and Piping
,”
Assessment Methodologies for Preventing Failure: Service Experience and Environmental Considerations
, Vol.
410–412
,
R.
Mohan
, ed.,
American Society of Mechanical Engineers
,
New York
, pp.
45
–
51
.
101.
Faidy
,
C.
,
Le Courtois
,
T.
,
de Fraguier
,
E.
,
Leduff
,
J.-A.
,
Lefrancois
,
A.
, and
Dechelotte
,
J.
,
2000
, “
Thermal Fatigue in French RHR System
,”
International Conference on Fatigue of Reactor Components
, Napa, CA, July 31–Aug. 2, pp. 6.3–6.12.
102.
Kussmaul
,
K.
,
Rintamaa
,
R.
,
Jansky
,
J.
,
Kemppainen
,
M.
, and
Törrönen
,
K.
,
1983
, “
On the Mechanism of Environmental Cracking Introduced by Cyclic Thermal Loading
,”
VTT Symposium, IAEA Specialists Meeting, Corrosion and Stress Corrosion of Steel Pressure Boundary Components and Steam Turbines
, Espoo, Finland, Vol.
43
, pp.
195
–
243
.
103.
Hickling
,
J.
,
2001
, “
Strain Induced Corrosion Cracking of Low-Alloy Reactor Pressure Vessel Steels Under BWR Conditions
,” Proceedings of the Tenth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems–Water Reactors,
F. P.
Ford
,
S. M.
Bruemmer
, and
G. S.
Was
, eds.,
The Minerals, Metals, and Materials Society
,
Warrendale, PA
, Paper No. 0156.
104.
Hickling
,
J.
,
2005
, “
Research and Service Experience With Environmentally Assisted Cracking of Low–Alloy Steel
,”
Power Plant Chem.
,
7
(
1
), pp.
4
–
15
.
105.
Iida
,
K.
,
1992
, “
A Review of Fatigue Failures in LWR Plants in Japan
,”
Nucl. Eng. Des.
,
138
(
3
), pp.
297
–
312
.
Google Scholar
Crossref
Search ADS
 
106.
Kussmaul
,
K.
,
Blind
,
D.
, and
Jansky
,
J.
,
1984
, “
Formation and Growth of Cracking in Feed Water Pipes and RPV Nozzles
,”
Nucl. Eng. Des.
,
81
(
1
), pp.
105
–
119
.
Google Scholar
Crossref
Search ADS
 
107.
Gordon
,
B. M.
,
Delwiche
,
D. E.
, and
Gordon
,
G. M.
,
1987
, “
Service Experience of BWR Pressure Vessels
,”
Performance and Evaluation of Light Water Reactor Pressure Vessels
, Vol.
119
,
American Society of Mechanical Engineers
,
New York
, pp.
9
–
17
.
108.
Lenz
,
E.
,
Stellwag
,
B.
, and
Wieling
,
N.
,
1983
, “
The Influence of Strain–Induced Corrosion Cracking on the Crack Initiation in Low-Alloy Steels in HT-Water–A Relation Between Monotonic and Cyclic Crack Initiation Behavior
,”
VTT Symposium, IAEA Specialists Meeting Corrosion and Stress Corrosion of Steel Pressure Boundary Components and Steam Turbines
, Espoo, Finland, Vol.
43
, pp.
243
–
267
.
109.
Hickling
,
J.
, and
Blind
,
D.
,
1986
, “
Strain-Induced Corrosion Cracking of Low-Alloy Steels in LWR Systems–Case Histories and Identification of Conditions Leading to Susceptibility
,”
Nucl. Eng. Des.
,
91
(
3
), pp.
305
–
330
.
Google Scholar
Crossref
Search ADS
 
110.
Shah
, V
. N.
,
Sattison
,
M. B.
,
Atwood
,
C. L.
,
Ware
,
A. G.
,
Grant
,
G. M.
, and
Hartley
,
R. S.
,
1998
, “
Assessment of Pressurized Water Reactor Primary System Leaks
,” Report No. NUREG/CR-6582, INEEL/EXT-97-01068.
111.
Hirschberg
,
P.
,
Deardorff
,
A. F.
, and
Carey
,
J.
,
2000
, “
Operating Experience Regarding Thermal Fatigue of Unisolable Piping Connected to PWR Reactor Coolant Systems
,”
International Conference on Fatigue of Reactor Components
, Napa, CA, July 31–Aug. 2, pp. 9.3–9.9.
112.
Sakai
,
T.
,
2000
, “
Leakage From CVCS Pipe of Regenerative Heat Exchanger Induced by High-Cycle Thermal Fatigue at Tsuruga Nuclear Power Station Unit 2
,”
International Conference on Fatigue of Reactor Components
, Napa, CA, July 31–Aug. 2.
113.
Hoshino
,
T.
,
Ueno
,
T.
,
Aoki
,
T.
, and
Kutomi
,
Y.
,
2000
, “
Leakage From CVCS Pipe of Regenerative Heat Exchanger Induced by High-Cycle Thermal Fatigue at Tsuruga Nuclear Power Station Unit 2
,”
8th International Conference on Nuclear Engineering
, 1.01 Operational Experience/Root Cause Failure Analysis, American Society of Mechanical Engineers, New York, Paper No. ICONE8-8615.
114.
NRC
,
1988
, “
Pressurizer Surge Line Thermal Stratification
,” U.S. Nuclear Regulatory Commission, Washington, DC,
NRC Bulletin No. 88–11
.
115.
Lenz
,
E.
,
Liebert
,
A.
, and
Wieling
,
N.
,
1990
, “
Thermal Stratification Tests to Confirm the Applicability of Laboratory Data on Strain-Induced Corrosion Cracking to Component Behavior
,”
3rd IAEA Specialists Meeting on Sub-Critical Crack Growth
, Moscow, Russia, pp.
67
–
91
.
116.
Kilian
,
R.
,
Hickling
,
J.
, and
Nickell
,
R.
,
2005
, “
Environmental Fatigue Testing of Stainless Steel Pipe Bends in Flowing, Simulated PWR Primary Water at 240 °C
,”
Third International Conference Fatigue of Reactor Components (MRP-151)
, Electric Power Research Institute, Palo Alto, CA, Report No. EPRI 1011958.
117.
Kilian
,
R.
,
2006
, “
Environmental Fatigue Testing of Type 304L Stainless Steel U-Bends in Simulated PWR Primary Water (MRP-188)
,” Materials Reliability Program, Electric Power Research Institute, Palo Alto, CA,
EPRI Report No. 1013028
.
118.
Hickling
,
J.
,
Kilian
,
R.
,
Spain
,
L.
, and
Carey
,
J.
,
2006
, “
Environmental Fatigue Testing of Type 304L Stainless Steel U-Bends in Simulated PWR Primary Water
,”
ASME
Paper No. PVP2006–ICPVT11-93318.
119.
Tokaji
,
K.
,
Ogawa
,
T.
, and
Osako
,
S.
,
1988
, “
The Growth of Microstructurally Small Fatigue Cracks in a Ferritic–Pearlitic Steel
,”
Fatigue Fract. Eng. Mater. Struct.
,
11
(
5
), pp.
331
–
342
.
Google Scholar
Crossref
Search ADS
 
120.
Dowling
,
N. E.
,
1977
, “
Crack Growth DuringLow-Cycle Fatigue of Smooth Axial Specimens
,”
Cyclic Stress–Strain and Plastic Deformation Aspects of Fatigue Crack Growth
, American Society for Testing and Materials, Philadelphia, PA, pp.
97
–
121
, Paper No. ASTM STP 637.
121.
Suresh
,
S.
, and
Ritchie
,
R. O.
,
1984
, “
Propagation of Short Fatigue Cracks
,”
Int. Met. Rev.
,
29
(6), pp.
445
–
476
.
Google Scholar
Crossref
Search ADS
 
122.
Tokaji
,
K.
, and
Ogawa
,
T.
,
1992
, “
The Growth of Microstructurally Small Fatigue Cracks in Metals
,”
Short Fatigue Cracks
,
M. J.
Miller
, and
E. R.
de los Rios
, eds.,
Mechanical Engineering Publication
,
London
, pp.
85
–
99
.
123.
de los Rios
,
E. R.
,
Tang
,
Z.
, and
Miller
,
K. J.
,
1984
, “
Short Crack Fatigue Behavior in a Medium Carbon Steel
,”
Fatigue Eng. Mater. Struct.
,
7
(
2
), pp.
97
–
108
.
Google Scholar
Crossref
Search ADS
 
124.
de los Rios
,
E. R.
,
Navarro
,
A.
, and
Hussain
,
K.
,
1992
, “
Microstructural Variations in Short Fatigue Crack Propagation of a C-Mn Steel
,”
Short Fatigue Cracks
,
M. J.
Miller
, and
E. R.
de los Rios
, eds.,
Mechanical Engineering Publication
,
London
, pp.
115
–
132
.
125.
Ford
,
F. P.
, and
Andresen
,
P. L.
,
1990
, “
Stress Corrosion Cracking of Low–Alloy Pressure Vessel Steel in 288 °C Water
,” Proceedings of the Third International Atomic Energy Agency Specialists' Meeting on Subcritical Crack Growth, Vol.
1
, pp.
37
–
56
, Paper No. NUREG/CP-0112.
126.
Ford
,
F. P.
,
1986
, “
Overview of Collaborative Research Into the Mechanisms of Environmentally Controlled Cracking in the Low Alloy Pressure Vessel Steel/Water System
,” Proceedings of the Second International Atomic Energy Agency Specialists' Meeting on Subcritical Crack Growth, Vol.
2
, pp.
3
–
71
, Paper No. NUREG/CP-0067, MEA-2090.
127.
Ford
,
F. P.
,
Taylor
,
D. F.
, and
Andresen
,
P. L.
,
1987
, “
Corrosion-Assisted Cracking of Stainless and Low-Alloy Steels in LWR Environments
,” Electric Power Research Institute, Palo Alto, CA,
Report No. EPRI NP-5064-M
.
128.
Ford
,
F. P.
,
Ranganath
,
S.
, and
Weinstein
,
D.
,
1993
, “
Environmentally Assisted Fatigue Crack Initiation in Low-Alloy Steels–A Review of the Literature and the ASME Code Design Requirements
,” Electric Power Research Institute, Palo Alto, CA,
Report No. EPRI TR-102765
.
129.
Ford
,
F. P.
,
1993
, “
Prediction of Corrosion Fatigue Initiation in Low–Alloy and Carbon Steel/ Water Systems at 288 °C
,” Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems–Water Reactors,
R. E.
Gold
, and
E. P.
Simonen
, eds.,
The Metallurgical Society
,
Warrendale, PA
, pp.
9
–
17
.
130.
Hänninen
,
H.
,
Törrönen
,
K.
, and
Cullen
,
W. H.
,
1986
, “
Comparison of Proposed Cyclic Crack Growth Mechanisms of Low Alloy Steels in LWR Environments
,” Proceedings in 2nd International Atomic Energy Agency Specialists' Meeting on Subcritical Crack Growth, NUREG/CP-0067, MEA–209.0, Vol. 2, pp. 73–97.
131.
Hänninen
,
H.
,
Törrönen
,
K.
,
Kempainen
,
M.
, and
Salonen
,
S.
,
1983
, “
On the Mechanisms of Environment Sensitive Cyclic Crack Growth of Nuclear Reactor Pressure Vessel Steels
,”
Corros. Sci.
,
23
(
6
), pp.
663
–
679
.
Google Scholar
Crossref
Search ADS
 
132.
Törrönen
,
K.
,
Kempainen
,
M.
, and
Hänninen
,
H.
,
1984
, “
Fractographic Evaluation of Specimens of A533B Pressure Vessel Steel
,” Final Report of EPRI, Contract RP 1325-7, Report No. NP3483.
133.
Atkinson
,
J. D.
,
Yu
,
J.
, and
Chen
,
Z.-Y.
,
1996
, “
An Analysis of the Effects of Sulfur Content and Potential on Corrosion Fatigue Crack Growth in Reactor Pressure Vessel Steels
,”
Corros. Sci.
,
38
(
5
), pp.
755
–
765
.
Google Scholar
Crossref
Search ADS
 
134.
Auten
,
T. A.
,
Hayden
,
S. Z.
, and
Emanuelson
,
R. H.
,
1993
, “
Fatigue Crack Growth Rate Studies of Medium Sulfur Low Alloy Steels Tested in High Temperature Water
,” Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems–Water Reactors,
R. E.
Gold
, and
E. P.
Simonen
, eds., The Metallurgical Society, Warrendale, PA, pp.
35
–
40
.
135.
Van Der Sluys
,
W. A.
, and
Emanuelson
,
R. H.
,
1993
, “
Environmentally Acceleration of Fatigue Crack Growth in Reactor Pressure Vessel Materials
,” Electric Power Research Institute, Palo Alto, CA, EPRI
Report No. TR-102796
.
136.
Van Der Sluys
,
W. A.
, and
Emanuelson
,
R. H.
,
1990
, “
Environmental Acceleration of Fatigue Crack Growth in Reactor Pressure Vessel Materials and Environments
,”
Environmentally Assisted Cracking: Science and Engineering
,
W. B.
Lisagor
,
T. W.
Crooker
,
B. N.
Leis
, eds.,
American Society for Testing and Materials
,
Philadelphia, PA
, pp.
117
–
135
.
137.
Atkinson
,
J. D.
, and
Forrest
,
J. E.
,
1986
, “
The Role of MnS Inclusions in the Development of Environmentally Assisted Cracking of Nuclear Reactor Pressure Vessel Steels
,”
2nd International Atomic Energy Agency Specialists' Meeting on Subcritical Crack Growth
, Vol.
2
, Paper No. NUREG/CP-0067, MEA-2090.
138.
Mehta
,
H. S.
,
Bhandari
,
S.
,
Jones
,
D.
,
Rahman
,
S.
,
Wilkowski
,
G.
, and
Yoon
,
K. K.
,
1996
, “
Initiation of Environmentally-Assisted Cracking in Low-Alloy Steels
,”
Fatigue and Fracture Vol. 1
, PVP-Volume 323,
American Society of Mechanical Engineers
,
New York
, pp.
269
–
289
.
139.
Oriani
,
R. A.
,
1972
, “
A Mechanistic Theory of Hydrogen Embrittlement of Steels
,”
Ber. Bunsengesellschaft Phys. Chem.
,
76
(8), pp.
848
–
857
.
140.
Beachem
,
C. D.
,
1972
, “
A New Model for Hydrogen Assisted Cracking
,”
Metall. Trans. A
,
3
(
2
), pp.
437
–
451
.
141.
Wu
,
X.
, and
Katada
,
Y.
,
2005
, “
Strain-Rate Dependence of Low Cycle Fatigue Behavior in a Simulated BWR Environment
,”
Corros. Sci.
,
47
(
6
), pp.
1415
–
1428
.
Google Scholar
Crossref
Search ADS
 
142.
Wu
,
X.
,
Han
,
E.
,
Ke
,
W.
, and
Katada
,
Y.
,
2007
, “
Effects of Loading Factors on Environmental Fatigue Behavior of Low-Alloy Pressure Vessel Steels in Simulated BWR Water
,”
Nucl. Eng. Des.
,
237
(12–13), pp.
1452
–
1459
.
Google Scholar
Crossref
Search ADS
 
143.
Higuchi
,
M.
,
Sakaguchi
,
K.
,
Nomura
,
Y.
, and
Hirano
,
A.
,
2007
, “
Final Proposal of Environmental Fatigue Life Correction Factor (Fen) for Structural Materials in LWR Water Environment
,”
ASME
Paper No. PVP2007-26100.
144.
Wu
,
X. Q.
, and
Katada
,
Y.
,
2004
, “
Influence of Cyclic Strain Rate on Environmentally Assisted Cracking Behavior of Pressure Vessel Steel in High-Temperature Water
,”
Mater. Sci. Eng. A
,
379
(1–2), pp.
58
–
71
.
Google Scholar
Crossref
Search ADS
 
145.
Wu
,
X.
, and
Katada
,
Y.
,
2004
, “
Corrosion Fatigue Behavior of Low-Alloy Pressure Vessel Steels in High Temperature Water Under Multi-Factor Conditions
,”
ASME J. Pressure Vessel Technol.
,
126
(
4
), pp.
466
–
472
.
Google Scholar
Crossref
Search ADS
 
146.
Wu
,
Q. X.
, and
Katada
,
Y.
,
2004
, “
Influence of Strain Rate Change on Corrosion Fatigue Behavior of A533B Steel in Simulated BWR Water
,”
J. Mater. Sci.
,
39
(
7
), pp.
2519
–
2522
.
Google Scholar
Crossref
Search ADS
 
147.
Wu
,
Q. X.
, and
Katada
,
Y.
,
2005
, “
Strain-Amplitude Dependent Fatigue Resistance of Low-Alloy Pressure Vessel Steels in High-Temperature Water
,”
J. Mater. Sci.
,
40
(
8
), pp.
1953
–
1958
.
Google Scholar
Crossref
Search ADS
 
148.
Wu
,
X.
,
Guan
,
H.
,
Han
,
E. H.
,
Ke
,
W.
, and
Katada
,
Y.
,
2006
, “
Influence of Surface Finish on Fatigue Cracking Behavior of Reactor Pressure Vessel Steel in High Temperature Water
,”
Mater. Corros.
,
57
(
11
), pp.
868
–
871
.
Google Scholar
Crossref
Search ADS
 
149.
Leax
,
T. R.
,
1999
, “
Statistical Models of Mean Stress and Water Environment Effects on the Fatigue Behavior of 304 Stainless Steel
,” Probabilistic and Environmental Aspects of Fracture and Fatigues, Vol.
386
,
S.
Rahman
 and
D. P.
Jones
, eds.,
American Society of Mechanical Engineers
,
New York
, pp.
229
–
239
.
Copyright © 2017 by ASME
You do not currently have access to this content.