-
1
-
-
0041698834
-
Rate approach for fatigue life reduction factor in LWR water environment
-
Asada, Y., 1993. Rate approach for fatigue life reduction factor in LWR water environment. WRC Progress Report, vol. No. XLVIII, 9/10, p. 148.
-
(1993)
WRC Progress Report
, vol.48
, Issue.9-10
, pp. 148
-
-
Asada, Y.1
-
2
-
-
0041698837
-
Protection against fatigue damage with respect to the environmental influence of LWR operating conditions
-
Bieniussa, K., Schulz, H., 1986. Protection against fatigue damage with respect to the environmental influence of LWR operating conditions. Nucl. Eng. Des. 94, 317-324.
-
(1986)
Nucl. Eng. Des.
, vol.94
, pp. 317-324
-
-
Bieniussa, K.1
Schulz, H.2
-
3
-
-
85040266899
-
BWR environmental cracking margins for carbon steel piping
-
Prepared by GE
-
BWR Environmental Cracking Margins for Carbon Steel Piping, 1982. EPRI Report No. NP-2406, Prepared by GE.
-
(1982)
EPRI Report No. NP-2406
-
-
-
4
-
-
0029425796
-
-
ASME, New York
-
Chopra, O.K., Shack, W.J., 1995. Effects of LWR environments on fatigue-life of carbon and low-Alloy steels, vol. PVP-306. ASME, New York.
-
(1995)
Effects of LWR Environments on Fatigue-life of Carbon and Low-alloy Steels
, vol.PVP-306
-
-
Chopra, O.K.1
Shack, W.J.2
-
7
-
-
0019369890
-
Low cycle fatigue of commercial piping steels in a BWR primary water environment
-
Hale, D.A., et al., 1981. Low cycle fatigue of commercial piping steels in a BWR primary water environment. J. Eng. Mater. Technol. Trans. ASME 103, 15-25.
-
(1981)
J. Eng. Mater. Technol. Trans. ASME
, vol.103
, pp. 15-25
-
-
Hale, D.A.1
-
8
-
-
0242433033
-
Fatigue strength correction factors for carbon and low-alloy steels in oxygen-containing high-temperature water
-
Higuchi, M., Iida, K., 1991. Fatigue strength correction factors for carbon and low-alloy steels in oxygen-containing high-temperature water. Nucl. Eng. Des. 129, 293-306.
-
(1991)
Nucl. Eng. Des.
, vol.129
, pp. 293-306
-
-
Higuchi, M.1
Iida, K.2
-
11
-
-
0041698833
-
Effects of LWR water environment on fatigue strength of several nuclear structural materials
-
New York City
-
Higuchi, M., Iida, K., Fukakura, J., Kobayashi, H., Miyazano, S., Nako, M., 1988. Effects of LWR Water environment on fatigue strength of several nuclear structural materials. Presented at ASME Code Subgroup on Fatigue Strength meeting, New York City.
-
(1988)
ASME Code Subgroup on Fatigue Strength Meeting
-
-
Higuchi, M.1
Iida, K.2
Fukakura, J.3
Kobayashi, H.4
Miyazano, S.5
Nako, M.6
-
12
-
-
0029424809
-
-
ASME, New York
-
Higuchi, M., Iida, K., Asada, Y., 1995. Effects of Strain Rate Change on Fatigue Life of Carbon Steel in High-Temperature Water, vol. PVP-306, ASME, New York.
-
(1995)
Effects of Strain Rate Change on Fatigue Life of Carbon Steel in High-Temperature Water
, vol.PVP-306
-
-
Higuchi, M.1
Iida, K.2
Asada, Y.3
-
13
-
-
0025263660
-
Low cycle fatigue crack initiation in SA210A1 carbon steel boiler tubing in contaminated boiler water
-
ASME, New York
-
James, B.A., Paul, L.D., Miglin, M.T., 1990. Low cycle fatigue crack initiation in SA210A1 carbon steel boiler tubing in contaminated boiler water. In: Fatigue Degradation and Fracture, vol. PVP-195. ASME, New York, pp. 13-19.
-
(1990)
Fatigue Degradation and Fracture
, vol.PVP-195
, pp. 13-19
-
-
James, B.A.1
Paul, L.D.2
Miglin, M.T.3
-
14
-
-
0029426689
-
-
ASME, New York
-
Kanasaki, H., Hayashi, M., Iida, K., Asada, Y., 1995. Effects of Temperature Change on Fatigue Life of Carbon Steel in High-Temperature Water, vol. PVP-306. ASME, New York.
-
(1995)
Effects of Temperature Change on Fatigue Life of Carbon Steel in High-Temperature Water
, vol.PVP-306
-
-
Kanasaki, H.1
Hayashi, M.2
Iida, K.3
Asada, Y.4
-
16
-
-
0004160152
-
-
NUREG/CR-6335
-
Keisler, J., Chopra, O.K., Shack, W.J., 1995. Fatigue strain-life behavior of carbon and low-alloy steels, austenitic stainless steels, and Alloy 600 in LWR Environments. NUREG/CR-6335.
-
(1995)
Fatigue Strain-life Behavior of Carbon and Low-alloy Steels, Austenitic Stainless Steels, and Alloy 600 in LWR Environments
-
-
Keisler, J.1
Chopra, O.K.2
Shack, W.J.3
-
17
-
-
0029425198
-
-
ASME, New York
-
Kishida, K., Suzuki, S., Asada, Y., 1995. Evaluation of Environmental Fatigue Life for Light Water Reactor Components, vol. PVP-306. ASME, New York.
-
(1995)
Evaluation of Environmental Fatigue Life for Light Water Reactor Components
, vol.PVP-306
-
-
Kishida, K.1
Suzuki, S.2
Asada, Y.3
-
18
-
-
0004237277
-
-
NUREG/CR-5999
-
Majumdar, S., Chopra, O.K., Shack, W.J., 1993. Interim fatigue design curves for carbon, low-alloy, and austenitic stainless steels in LWR environments. NUREG/CR-5999.
-
(1993)
Interim Fatigue Design Curves for Carbon, Low-alloy, and Austenitic Stainless Steels in LWR Environments
-
-
Majumdar, S.1
Chopra, O.K.2
Shack, W.J.3
-
19
-
-
0003726890
-
An environmental factor approach to account for reactor water effects in light water reactor pressure vessel and piping fatigue evaluations
-
Mehta, H.S., Gosselin, S.R., 1995. An environmental factor approach to account for reactor water effects in light water reactor pressure vessel and piping fatigue evaluations. EPRI Report No. TR-105759.
-
(1995)
EPRI Report No. TR-105759
-
-
Mehta, H.S.1
Gosselin, S.R.2
-
20
-
-
0042700598
-
-
ASME, New York
-
Mehta, H.S., Ranganath, S., 1992. An Environmental Fatigue Stress Rule for Carbon Steel Reactor Piping, vol. PVP-241. ASME, New York.
-
(1992)
An Environmental Fatigue Stress Rule for Carbon Steel Reactor Piping
, vol.PVP-241
-
-
Mehta, H.S.1
Ranganath, S.2
-
21
-
-
0041698828
-
Application of environmental fatigue stress rules to carbon steel reactor piping
-
Mehta, H.S., Ranganath, S., Weinstein, D., 1986. Application of environmental fatigue stress rules to carbon steel reactor piping. EPRI Report No. NP-4644.
-
(1986)
EPRI Report No. NP-4644
-
-
Mehta, H.S.1
Ranganath, S.2
Weinstein, D.3
-
22
-
-
0039122934
-
Low-cycle fatigue behavior of low-alloy steels in high-temperature pressurized water
-
Anaheim, CA
-
Nagata, N., Sato, S., Katada, Y., 1989. Low-cycle fatigue behavior of low-alloy steels in high-temperature pressurized water. Trans. 10th Int. Conf. on Structural Mechanics in Reactor Technology, Anaheim, CA.
-
(1989)
Trans. 10th Int. Conf. on Structural Mechanics in Reactor Technology
-
-
Nagata, N.1
Sato, S.2
Katada, Y.3
-
24
-
-
0043201747
-
Environmentally assisted cracking in light water reactors
-
NUREG/CR-4667, August
-
NUREG/CR-4667, 1994. Environmentally assisted cracking in light water reactors. Semiannual Reports: vol. 12 (August 1991), vol. 13 (March 1992), vol. 16 (September 1993) and vol. 17 (June 1994).
-
(1991)
Semiannual Reports
, vol.12
-
-
-
25
-
-
0041698827
-
-
March
-
NUREG/CR-4667, 1994. Environmentally assisted cracking in light water reactors. Semiannual Reports: vol. 12 (August 1991), vol. 13 (March 1992), vol. 16 (September 1993) and vol. 17 (June 1994).
-
(1992)
Semiannual Reports
, vol.13
-
-
-
26
-
-
0043201750
-
-
September
-
NUREG/CR-4667, 1994. Environmentally assisted cracking in light water reactors. Semiannual Reports: vol. 12 (August 1991), vol. 13 (March 1992), vol. 16 (September 1993) and vol. 17 (June 1994).
-
(1993)
Semiannual Reports
, vol.16
-
-
-
27
-
-
0042199426
-
-
June
-
NUREG/CR-4667, 1994. Environmentally assisted cracking in light water reactors. Semiannual Reports: vol. 12 (August 1991), vol. 13 (March 1992), vol. 16 (September 1993) and vol. 17 (June 1994).
-
(1994)
Semiannual Reports
, vol.17
-
-
-
28
-
-
0043201744
-
-
ASME, New York
-
O'Donnel, T.P., O'Donnel, W.J., 1995. Cyclic Rate-Dependent Fatigue Life In Reactor Water, vol. PVP-306. ASME, New York.
-
(1995)
Cyclic Rate-Dependent Fatigue Life in Reactor Water
, vol.PVP-306
-
-
O'Donnel, T.P.1
O'Donnel, W.J.2
-
29
-
-
0043201738
-
Synthesis of S/N and da/dN life evaluation technologies
-
Pittsburgh, ASME Publication
-
O'Donnel, W.J., 1988. Synthesis of S/N and da/dN Life Evaluation technologies, PVP Conference, Pittsburgh, vol. 88-PVP-10. ASME Publication.
-
(1988)
PVP Conference
, vol.88 PVP-10
-
-
O'Donnel, W.J.1
-
31
-
-
85167825214
-
-
ASTM STP, Philadelphia, PA
-
Ranganath, S., Kass, J.N., Heald, J.D., 1982. Fatigue Behavior of Carbon Steel Components in High-Temperature Water Environments, vol. 770. ASTM STP, Philadelphia, PA, pp. 436-459.
-
(1982)
Fatigue Behavior of Carbon Steel Components in High-Temperature Water Environments
, vol.770
, pp. 436-459
-
-
Ranganath, S.1
Kass, J.N.2
Heald, J.D.3
-
32
-
-
0003842228
-
-
Section III, Division 1. ASME Boiler and Pressure Vessel Code, American Society of Mechanical Engineers
-
Rules for Construction of Nuclear Power Plant Components, 1992. Section III, Division 1. ASME Boiler and Pressure Vessel Code, American Society of Mechanical Engineers.
-
(1992)
Rules for Construction of Nuclear Power Plant Components
-
-
-
33
-
-
0041698815
-
-
Pressurized, Water Cooled Systems, PB 151987, U.S. Dept. of Commerce, Office of Technical Services, 1 Dec. 1958 Revision
-
Tentative Structural Design Basis for Reactor Pressure Vessels and Directly Associated Components, 1958. Pressurized, Water Cooled Systems, PB 151987, U.S. Dept. of Commerce, Office of Technical Services, 1 Dec. 1958 Revision.
-
(1958)
Tentative Structural Design Basis for Reactor Pressure Vessels and Directly Associated Components
-
-
-
34
-
-
0024876309
-
Fatigue life response of ASME SA 106-B steel in pressurized water reactor environments
-
Terrel, J.B., 1989. Fatigue life response of ASME SA 106-B steel in pressurized water reactor environments. Int. J. Press. Vessels Pip. 39, 345-374.
-
(1989)
Int. J. Press. Vessels Pip.
, vol.39
, pp. 345-374
-
-
Terrel, J.B.1
-
35
-
-
0029427205
-
-
ASME, New York
-
Van Der Sluys, W.A., Yukawa, S., 1995. Status of PVRC Evaluation of LWR Coolant Environmental Effects on the S-N Fatigue Properties of Pressure Boundary Materials, vol. PVP-306. ASME, New York.
-
(1995)
Status of PVRC Evaluation of LWR Coolant Environmental Effects on the S-N Fatigue Properties of Pressure Boundary Materials
, vol.PVP-306
-
-
Van Der Sluys, W.A.1
Yukawa, S.2
-
36
-
-
0027876284
-
Evaluation of the available data on the effect of the environment on the low cycle fatigue properties in light water reactor environments
-
TMS/NACE, 1-5 August, San Diego, CA
-
Van Der Sluys, W.A., 1993. Evaluation of the available data on the effect of the environment on the low cycle fatigue properties in light water reactor environments. Presented at the 6th Int. Symp. on Environmental degradation in Nuclear Power Systems - Water Reactors. TMS/NACE, 1-5 August, San Diego, CA.
-
(1993)
6th Int. Symp. on Environmental Degradation in Nuclear Power Systems - Water Reactors
-
-
Van Der Sluys, W.A.1
|