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International review of nuclear reactor pressure vessel surveillance programs : pbk

International review of nuclear reactor pressure vessel surveillance programs : pbk
Paper図書
editors: William L. Server and Milan BrumovskýASTM Internationalc2018
Other Libraries in Japan

In-place thermal annealing of nuclear reactor pressure vessels / prepared by W.L. Server

In-place thermal annealing of nuclear reactor pressure vessels / prepared by W.L. Server
Microform図書
1985<YCA-Y 3.N 88:25/4212>
National Diet Library

PRIMER: FRACTURE MECHANICS IN THE NUCLEAR POWER INDUSTRY (EPRI ; EPRI-NP-5792-SR)

PRIMER: FRACTURE MECHANICS IN THE NUCLEAR POWER INDUSTRY (EPRI ; EPRI-NP-5792-SR)
Paper図書
WESSEL, E.T./SERVER, W.L.Electric Power Research Institute(Electric Power Research Institute)1990.
Other Libraries in Japan

Small specimen test techniques applied to nuclear reactor vessel thermal annealing and plant life extension

Small specimen test techniques applied to nuclear reactor vessel thermal annealing and plant life extension
Paper図書
William R. Corwin, Fahmy M. Haggag, and William L. Server, editorsASTMc1993
Other Libraries in Japan

DA/DN; A Computer Program for Pipe Fatigue Crack Growth (EPRI ; EPRI-NP-5720)

DA/DN; A Computer Program for Pipe Fatigue Crack Growth (EPRI ; EPRI-NP-5720)
Paper図書
Quinones, D.F./Server, W.L.Electric Power Research Institute(Electric Power Research Institute)1988.
Other Libraries in Japan

Approach for Predicting Reference Fracture Toughness in Irradiated Vessel Materials (EPRI ; EPRI-NP-5793)

Approach for Predicting Reference Fracture Toughness in Irradiated Vessel Materials (EPRI ; EPRI-NP-5793)
Paper図書
Server, W.L./Caldwell, H.M.Electric Power Research Institute(Electric Power Research Institute)1988.
Other Libraries in Japan

APPROACH FOR ESTIMATING POST-ANNUAL REIRRADIATION EMBRITTLEMENT OF REACTOR VESSEL STEELS. (EGG ; EGG-M-01485)

APPROACH FOR ESTIMATING POST-ANNUAL REIRRADIATION EMBRITTLEMENT OF REACTOR VESSEL STEELS. (EGG ; EGG-M-01485)
Paper図書
SERVER, W.L.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1985.
Other Libraries in Japan

In-Place Thermal Annealing of Nuclear Reactor Pressure Vessels (NUREG ; NUREG/CR-4212; EGG-MS-6708)

In-Place Thermal Annealing of Nuclear Reactor Pressure Vessels (NUREG ; NUREG/CR-4212; EGG-MS-6708)
Paper図書
Server, W.L.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1985.
Other Libraries in Japan

LIFE EXTENSION OF COMPONENTS WITH HIGH CUMULATIVE FATIGUE USAGE. (EGG ; EGG-M-16385)

LIFE EXTENSION OF COMPONENTS WITH HIGH CUMULATIVE FATIGUE USAGE. (EGG ; EGG-M-16385)
Paper図書
SERVER, W.L.EG and G Idaho, Inc.(EG and G Idaho, Inc.)1985.
Other Libraries in Japan

THERMAL AND STRUCTURAL ANALYSIS OF LIGHT-WATER REACTOR VESSEL IN-PLACE ANNEALING. (EGG ; EGG-M-19684)

THERMAL AND STRUCTURAL ANALYSIS OF LIGHT-WATER REACTOR VESSEL IN-PLACE ANNEALING. (EGG ; EGG-M-19684)
Paper図書
SERVER, W.L.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1984.
Other Libraries in Japan

THERMAL AND STRUCTURAL ANALYSIS OF LIGHT-WATER REACTOR VESSEL IN-PLACE ANNEALING (CONF ; CONF-8410142-58)

THERMAL AND STRUCTURAL ANALYSIS OF LIGHT-WATER REACTOR VESSEL IN-PLACE ANNEALING (CONF ; CONF-8410142-58)
Paper図書
1984.
Other Libraries in Japan
  • Author HeadingServer, W L Houstrup, J P

EVALUATION OF SYSTEM REQUIREMENTS AND STANDARDS DEVELOPMENT FOR THERMAL ANNEALING OF REACTOR PRESSURE VESSELS. (NUREG ; NUREG-CR-2780)

EVALUATION OF SYSTEM REQUIREMENTS AND STANDARDS DEVELOPMENT FOR THERMAL ANNEALING OF REACTOR PRESSURE VESSELS. (NUREG ; NUREG-CR-2780)
Paper図書
SERVER, W.L.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1983.
Other Libraries in Japan

Postirradiation Annealing Recovery of High Copper Reactor Pressure Vessel Weld Metal Toughness Properties (NUREG ; NUREG/CR-3582; EGG-MS-6388)

Postirradiation Annealing Recovery of High Copper Reactor Pressure Vessel Weld Metal Toughness Properties (NUREG ; NUREG/CR-3582; EGG-MS-6388)
Paper図書
Server, W.L.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1983.
Other Libraries in Japan

Evaluation of System Requirements and Standards Development for Thermal Annealing of Reactor Pressure Vessels. Progress report March - September 1982. (NUREG ; NUREG/CR-2780; EGG-FM-6174)

Evaluation of System Requirements and Standards Development for Thermal Annealing of Reactor Pressure Vessels. Progress report March - September 1982. (NUREG ; NUREG/CR-2780; EGG-FM-6174)
Paper図書
Server, W.L.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1983.
Other Libraries in Japan

EFFECTS OF IRRADIATION FLUENCE AND CREEP ON FRACTURE TOUGHNESS OF 347/348 STAINLESS STEEL (CONF ; CONF-840604-20)

EFFECTS OF IRRADIATION FLUENCE AND CREEP ON FRACTURE TOUGHNESS OF 347/348 STAINLESS STEEL (CONF ; CONF-840604-20)
Paper図書
1984.
Other Libraries in Japan
  • Author HeadingHaggag, F M Server, W L Reuter, W G Beeston, J M

Case study of the propagation of a small flaw under PWR loading conditions and comparison with the ASME code design life: comparison of ASME Code sections III and XI (ORNL ; ORNL-6099)

Case study of the propagation of a small flaw under PWR loading conditions and comparison with the ASME code design life: comparison of ASME Code sections III and XI (ORNL ; ORNL-6099)
Paper図書
Oak Ridge National Laboratory(Oak Ridge National Laboratory)1984.
Other Libraries in Japan

NUCLEAR PRESSURE VESSEL STEEL DATA BASE. (EPRI ; EPRI-NP-933)

NUCLEAR PRESSURE VESSEL STEEL DATA BASE. (EPRI ; EPRI-NP-933)
Paper図書
SERVER, W.L.(et al.)Electric Power Research Institute(Electric Power Research Institute)1978.
Other Libraries in Japan

"Combined RPV Surveillance Testing Program for CP&L Brunswick Units 1 & 2."

"Combined RPV Surveillance Testing Program for CP&L Brunswick Units 1 & 2."
Paper図書
BEAUDOIN, B. F.//GRIESBACH, T. J.//SERVER, W. L.ATI CONSULTING1997/10/29.
Other Libraries in Japan

EXPERIMENTAL AND STATISTICAL REQUIREMENTS FOR DEVELOPING A WELL-DEFINED K/SUB IR/ CURVE. FINAL REPORT. (EPRI ; EPRI-NP-372)

EXPERIMENTAL AND STATISTICAL REQUIREMENTS FOR DEVELOPING A WELL-DEFINED K/SUB IR/ CURVE. FINAL REPORT. (EPRI ; EPRI-NP-372)
Paper図書
SERVER, W.L.(et al.)Electric Power Research Institute(Electric Power Research Institute)1977.
Other Libraries in Japan

FRACTURE TOUGHNESS DATA FOR FERRITIC NUCLEAR PRESSURE VESSEL MATERIALS. TASK B - LABORATORY, ETC... (PB ; PB-252210)

FRACTURE TOUGHNESS DATA FOR FERRITIC NUCLEAR PRESSURE VESSEL MATERIALS. TASK B - LABORATORY, ETC... (PB ; PB-252210)
Paper図書
SERVER, W.L.1976.
Other Libraries in Japan
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