-
1
-
-
5544263441
-
Rules for construction of nuclear power plant components
-
American Society of Mechanical Engineers
-
"Rules for Construction of Nuclear Power Plant Components," Section III, Division 1, 1992 ASME Boiler and Pressure Vessel Code, American Society of Mechanical Engineers.
-
Section III, Division 1, 1992 ASME Boiler and Pressure Vessel Code
-
-
-
2
-
-
0030365980
-
An environmental factor approach to account for reactor water effects in light water reactor pressure vessel and piping fatigue evaluations
-
December. Also, ASME PVP-Volume
-
Mehta, H.S. and Gosselin, S.R., "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, December 1995. Also, ASME PVP-Volume 323 (1996).
-
(1995)
EPRI Report No. TR-105759
, vol.323
-
-
Mehta, H.S.1
Gosselin, S.R.2
-
3
-
-
0032071553
-
Environmental factor approach to account for water effects in pressure vessel and piping fatigue evaluations
-
Mehta, H.S. and Gosselin, S.R., "Environmental Factor Approach to Account for Water Effects in Pressure Vessel and Piping Fatigue Evaluations," Nuclear Engineering and Design Journal, Volume 181 (1998), pp. 175-197.
-
(1998)
Nuclear Engineering and Design Journal
, vol.181
, pp. 175-197
-
-
Mehta, H.S.1
Gosselin, S.R.2
-
4
-
-
0004160152
-
-
NUREG/CR-6335, August
-
J. Keisler, O.K. Chopra and W.J. Shack, "Fatigue Strain-Life Behavior of Carbon and Low-Alloy Steels, Austenitic Stainless Steels, and Alloy 600 in LWR Environments," NUREG/CR-6335, August 1995.
-
(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
-
6
-
-
0004237277
-
-
NUREG/CR-5999, April
-
Majumdar, S., Chopra, O.K. and Shack, W.J., "Interim Fatigue Design Curves for Carbon, Low-Alloy, and Austenitic Stainless Steels in LWR Environments," NUREG/CR-5999, April 1993.
-
(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
-
7
-
-
0343914732
-
Environmental fatigue evaluations of representative BWR components
-
June
-
(a) Mehta, H.S., "Environmental Fatigue Evaluations of Representative BWR Components," EPRI Report No. TR-107943, June 1998.
-
(1998)
EPRI Report No. TR-107943
-
-
Mehta, H.S.1
-
9
-
-
0343043113
-
Evaluation of thermal fatigue effects on systems requiring aging management review for license renewal for the Calvert Cliffs Nuclear Power Plant
-
December
-
Gerber, D.A. and Stevens, G.L., "Evaluation of Thermal Fatigue Effects on Systems Requiring Aging Management Review for License Renewal for the Calvert Cliffs Nuclear Power Plant," EPRI Report No. TR-107515, December 1997.
-
(1997)
EPRI Report No. TR-107515
-
-
Gerber, D.A.1
Stevens, G.L.2
-
10
-
-
0343914731
-
Evaluation of environmental thermal fatigue effects on selected components in boiling water reactor
-
April
-
Stevens, G.L., "Evaluation of Environmental Thermal Fatigue Effects on Selected Components in Boiling Water Reactor," EPRI Report No. TR-110356, April 1998.
-
(1998)
EPRI Report No. TR-110356
-
-
Stevens, G.L.1
-
11
-
-
0343478981
-
Evaluation of environmental fatigue effects for a Westinghouse Nuclear Power Plant
-
April
-
Gerber, D.A., "Evaluation of Environmental Fatigue Effects for a Westinghouse Nuclear Power Plant," EPRI Report No. TR-110043, April 1998.
-
(1998)
EPRI Report No. TR-110043
-
-
Gerber, D.A.1
-
17
-
-
0017556701
-
Fatigue design criteria for pressure vessel alloys
-
(a) Jaske, C.E. and O'Donnell, W.J., "Fatigue Design Criteria for Pressure Vessel Alloys," Transactions of ASME Journal of Pressure Vessel Technology, Vol. 99, 1977, pp. 584-592.
-
(1977)
Transactions of ASME Journal of Pressure Vessel Technology
, vol.99
, pp. 584-592
-
-
Jaske, C.E.1
O'Donnell, W.J.2
-
18
-
-
0342608962
-
Discussions: Fatigue design criteria for pressure vessel alloys
-
(b) "Discussions: Fatigue Design Criteria for Pressure Vessel Alloys," Transactions of ASME Journal of Pressure Vessel Technology, Vol. 100, 1978, pp. 236-243.
-
(1978)
Transactions of ASME Journal of Pressure Vessel Technology
, vol.100
, pp. 236-243
-
-
-
19
-
-
0004382460
-
-
NUREG/CR-6237, August
-
Keisler, J., Chopra, O.K. and Shack, W.J., "Statistical Analysis of Fatigue Strain-Life Data for Carbon and Low-Alloy Steels," NUREG/CR-6237, August 1994.
-
(1994)
Statistical Analysis of Fatigue Strain-life Data for Carbon and Low-alloy Steels
-
-
Keisler, J.1
Chopra, O.K.2
Shack, W.J.3
-
20
-
-
0031628539
-
-
July
-
Itatani, M, Iida, K. And Ogawa, K, "Effect of Loading Rate on the Fatigue Strength of Notched Carbon Steel in High Temperature Water," ASME PVP Volume 374, July 1998.
-
(1998)
"Effect of Loading Rate on the Fatigue Strength of Notched Carbon Steel in High Temperature Water," ASME PVP
, vol.374
-
-
Itatani, M.1
Iida, K.2
Ogawa, K.3
-
21
-
-
0342608912
-
PVRC progress report to BNCS, October 9, 1998, Atlanta, Georgia
-
Sept./Oct.
-
Yukawa, S., "PVRC Progress Report to BNCS, October 9, 1998, Atlanta, Georgia," Welding Research Council Progress Reports, Volume LIII, No. 9/10, Sept./Oct. 1998.
-
(1998)
Welding Research Council Progress Reports
, vol.53
, Issue.9-10
-
-
Yukawa, S.1
|