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Steam generator tube failures NUREG/CR-6365 TI96 010605

Steam generator tube failures NUREG/CR-6365 TI96 010605
Microform規格・テクニカルリポート類
MacDonald, P. E, Shah, V. N, Ward, L. W, Ellison, P. G1996<LS-TI96/010605>
National Diet Library

Advanced nondestructive examination technologies for measuring fatigue damage in nuclear power plant components INEL-95/00555 DE96 003338 CONF-95102671

Advanced nondestructive examination technologies for measuring fatigue damage in nuclear power plant components INEL-95/00555 DE96 003338 CONF-95102671
Microform規格・テクニカルリポート類
MacDonald, P. E, Shah, V. N, Akers, D. W1995<LS-DE96/003338>
National Diet Library

Assessment of pressurized water reactor controlrod drive mechhanism nozzle cracking NUREG/CR-6245 TI95 004202 EGG-2715

Assessment of pressurized water reactor controlrod drive mechhanism nozzle cracking NUREG/CR-6245 TI95 004202 EGG-2715
Microform規格・テクニカルリポート類
Shah, V. N, Ware, A. G, Porter, A. M1994<LS-TI95/004202>
National Diet Library

Advanced nondestructive examination technologies for measuring fatigue damage in nuclear power plant components (INEL ; INEL-95/00555; CONF-9510267-1; DE96003338)

Advanced nondestructive examination technologies for measuring fatigue damage in nuclear power plant components (INEL ; INEL-95/00555; CONF-9510267-1; DE96003338)
Paper図書
MacDonald, P.E., Shah, V.N., Akers, D.W.Lockheed Idaho Technologies Co.1995.12.
Other Libraries in Japan

INSIGHTS FOR AGING MANAGEMENT OF LIGHT WATER REACTOR COMPONENTS: METAL CONTAINMENTS. (NUREG ; NUREG/CR-5314-VOL.5)

INSIGHTS FOR AGING MANAGEMENT OF LIGHT WATER REACTOR COMPONENTS: METAL CONTAINMENTS. (NUREG ; NUREG/CR-5314-VOL.5)
Paper図書
SHAH, V.N.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1994.
Other Libraries in Japan

Seismic effects in PVP components : presented at the 1984 Pressure Vessel and Piping Conference and Exhibition, San Antonio, Texas, June 17-21, 1984 / sponsored by the Pressure Vessels and Piping Division, ASME ; edited by V.N. Shah, D.C. Ma. (PVP ; vol. 88)

Seismic effects in PVP components : presented at the 1984 Pressure Vessel and Piping Conference and Exhibition, San Antonio, Texas, June 17-21, 1984 / sponsored by the Pressure Vessels and Piping Division, ASME ; edited by V.N. Shah, D.C. Ma. (PVP ; vol. 88)
Paper図書
American Society of Mechanical Engineersc1984.<M15-A4522>
National Diet Library

ASSESSMENT OF PRESSURIZED WATER REACTOR CONTROL ROD DRIVE MECHANISM NOZZLE CRACKING. (NUREG ; NUREG/CR-6245)

ASSESSMENT OF PRESSURIZED WATER REACTOR CONTROL ROD DRIVE MECHANISM NOZZLE CRACKING. (NUREG ; NUREG/CR-6245)
Paper図書
SHAH, V.N.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1994.
Other Libraries in Japan

NEED FOR ASME CODE CHANGES FOR RELIABLE CHARACTERIZATION OF THERMAL FATIGUE CRACKS IN CLASS 1 COMPONENTS. (EGG ; EGG-M-91100)

NEED FOR ASME CODE CHANGES FOR RELIABLE CHARACTERIZATION OF THERMAL FATIGUE CRACKS IN CLASS 1 COMPONENTS. (EGG ; EGG-M-91100)
Paper図書
SHAH, V.N.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1991.
Other Libraries in Japan

RESIDUAL LIFE ASSESSMENT OF MAJOR LIGHT WATER REACTOR COMPONENTS: OVERVIEW. (NUREG ; NUREG-CR-4731-VOL.2)

RESIDUAL LIFE ASSESSMENT OF MAJOR LIGHT WATER REACTOR COMPONENTS: OVERVIEW. (NUREG ; NUREG-CR-4731-VOL.2)
Paper図書
SHAH, V.N.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1989.
Other Libraries in Japan

RESEARCH NEEDS FOR FATIGUE DAMAGE ASSESSMENT IN PWR SURGE AND SPRAY PIPING. (EGG ; EGG-M-89093)

RESEARCH NEEDS FOR FATIGUE DAMAGE ASSESSMENT IN PWR SURGE AND SPRAY PIPING. (EGG ; EGG-M-89093)
Paper図書
SHAH, V.N.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1989.
Other Libraries in Japan

AGING DEGRADATION OF MAJOR LWR (LIGHT WATER REACTOR) COMPONENTS. (EGG ; EGG-M-31787)

AGING DEGRADATION OF MAJOR LWR (LIGHT WATER REACTOR) COMPONENTS. (EGG ; EGG-M-31787)
Paper図書
SHAH, V.N.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1988.
Other Libraries in Japan

Life extension and assessment: Nuclear and fossil power-plant components: Presented at the ASME pressure vessels and piping conference, 1988. (PVP-V.138) (NDE-V.4)

Life extension and assessment: Nuclear and fossil power-plant components: Presented at the ASME pressure vessels and piping conference, 1988. (PVP-V.138) (NDE-V.4)
Paper図書
Jaske, C.E.(ed.)/Shah, V.N.(ed.)/and othersASME1988.
Other Libraries in Japan

TECHNICAL SAFETY ISSUES RELATED TO RESIDUAL LIFE ASSESSMENT OF MAJOR LWR (LIGHT WATER REACTOR) COMPONENTS AND STRUCTURES. (EGG ; EGG-M-21787)

TECHNICAL SAFETY ISSUES RELATED TO RESIDUAL LIFE ASSESSMENT OF MAJOR LWR (LIGHT WATER REACTOR) COMPONENTS AND STRUCTURES. (EGG ; EGG-M-21787)
Paper図書
SHAH, V.N.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1987.
Other Libraries in Japan

RESIDUAL LIFE ASSESSMENT OF LIGHT WATER REACTOR PRESSURE VESSELS. (EGG ; EGG-M-15187)

RESIDUAL LIFE ASSESSMENT OF LIGHT WATER REACTOR PRESSURE VESSELS. (EGG ; EGG-M-15187)
Paper図書
SHAH, V.N.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1987.
Other Libraries in Japan

RESIDUAL LIFE ASSESSMENT OF MAJOR PWR COMPONENTS. (EGG ; EGG-M-22986)

RESIDUAL LIFE ASSESSMENT OF MAJOR PWR COMPONENTS. (EGG ; EGG-M-22986)
Paper図書
SHAH, V.N.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1986.
Other Libraries in Japan

CREEP RUPTURE FAILURE OF REACTOR PRESSURE VESSEL LOWER HEAD DURING SEVERE ACCIDENTS (CONF ; CONF-860908-45)

CREEP RUPTURE FAILURE OF REACTOR PRESSURE VESSEL LOWER HEAD DURING SEVERE ACCIDENTS (CONF ; CONF-860908-45)
Paper図書
1986.
Other Libraries in Japan
  • Author HeadingShah, V N

Residual life assessment of major light water reactor components: Overview, V.1. (NUREG ; NUREG/CR-4731; EGG-2469-V.1)

Residual life assessment of major light water reactor components: Overview, V.1. (NUREG ; NUREG/CR-4731; EGG-2469-V.1)
Paper図書
Shah, V.N.(ed.)/Macdonald, P.E.(ed.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1987.
Other Libraries in Japan

CREEP RUPTURE FAILURE OF REACTOR PRESSURE VESSEL LOWER HEAD DURING SEVERE ACCIDENTS. (EGG ; EGG-M-06886)

CREEP RUPTURE FAILURE OF REACTOR PRESSURE VESSEL LOWER HEAD DURING SEVERE ACCIDENTS. (EGG ; EGG-M-06886)
Paper図書
SHAH, V.N.EG and G Idaho, Inc.(EG and G Idaho, Inc.)1986.
Other Libraries in Japan

CLADDING CREEPDOWN MODEL FOR FRAPCON-2. (EGG ; EGG-RST-6811)

CLADDING CREEPDOWN MODEL FOR FRAPCON-2. (EGG ; EGG-RST-6811)
Paper図書
SHAH, V.N.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1985.
Other Libraries in Japan

FUEL COMPLIANCE MODEL FOR PELLET-CLADDING MECHANICAL INTERACTION. (EGG ; EGG-M-15284)

FUEL COMPLIANCE MODEL FOR PELLET-CLADDING MECHANICAL INTERACTION. (EGG ; EGG-M-15284)
Paper図書
SHAH, V.N.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1985.
Other Libraries in Japan
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