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Component evaluation for intersystem loss-of-coolant accidents in advanced light water reactors NUREG/CR-6121 TI94 017139

Component evaluation for intersystem loss-of-coolant accidents in advanced light water reactors NUREG/CR-6121 TI94 017139
Microform規格・テクニカルリポート類
Ware, A. G1994<LS-TI94/017139>
National Diet Library

Estimates of margins in ASME Code strength values for stainless steel nuclear piping INEL-95/00197 DE96 002047 CONF-950740102

Estimates of margins in ASME Code strength values for stainless steel nuclear piping INEL-95/00197 DE96 002047 CONF-950740102
Microform規格・テクニカルリポート類
Ware, A. G1995<LS-DE96/002047>
National Diet Library

Application of environmentally-corrected fatigue curves to nuclear power plant components INEL-96/00105 DE96 009012 CONF-96070610

Application of environmentally-corrected fatigue curves to nuclear power plant components INEL-96/00105 DE96 009012 CONF-96070610
Microform規格・テクニカルリポート類
Ware, A. G, Morton, D. K, Nitzel, M. E1996<LS-DE96/009012>
National Diet Library

Effects on fatigue life of gate valves due to higher torque switch settings during operability testing INEL-95/0557 DE96 004130

Effects on fatigue life of gate valves due to higher torque switch settings during operability testing INEL-95/0557 DE96 004130
Microform規格・テクニカルリポート類
Richins, W. D, Snow, S. D, Miller, G. K, Russell, M. J, Ware, A. G1995<LS-DE96/004130>
National Diet Library

Application of NUREG/CR-5999 interim fatigue curves to selected nuclear power plant components NUREG/CR-6260 TI95 009088 INEL-95/0045

Application of NUREG/CR-5999 interim fatigue curves to selected nuclear power plant components NUREG/CR-6260 TI95 009088 INEL-95/0045
Microform規格・テクニカルリポート類
Ware, A. G, Morton, D. K, Nitzel, M. E1995<LS-TI95/009088>
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

ASSESSMENT OF FIELD EXPERIENCE RELATED TO PRESSURIZED WATER REACTOR PRIMARY SYSTEM LEAKS. (INEEL ; INEEL/CON-99-00037; DE00009237)

ASSESSMENT OF FIELD EXPERIENCE RELATED TO PRESSURIZED WATER REACTOR PRIMARY SYSTEM LEAKS. (INEEL ; INEEL/CON-99-00037; DE00009237)
Paper図書
WARE, A.G.(et al.)1999.
Other Libraries in Japan
  • Author HeadingWARE, A.G.

LESSONS LEARNED FROM DROP TESTING. (INEEL ; INEEL/CON-99-00137; DE00007639)

LESSONS LEARNED FROM DROP TESTING. (INEEL ; INEEL/CON-99-00137; DE00007639)
Paper図書
WARE, A.G.(et al.)1999.
Other Libraries in Japan
  • Author HeadingWARE, A.G.

Comparison of ASME Code NB-3200 and NB-3600 results for fatigue analysis of B31.1 branch nozzles (INEL ; INEL-96/00044; CONF-960706-11; TI96009015)

Comparison of ASME Code NB-3200 and NB-3600 results for fatigue analysis of B31.1 branch nozzles (INEL ; INEL-96/00044; CONF-960706-11; TI96009015)
Paper図書
Nitzel, M.E., Ware, A.G., Morton, D.K.Lockheed Idaho Technologies Co.1996.6.
Other Libraries in Japan
  • Author HeadingNitzel, M.E. Ware, A.G. Morton, D.K.

Estimates of margins in ASME Code strength values for stainless steel nuclear piping (INEL ; INEL-95/00197; CONF-950740-102; DE96002047)

Estimates of margins in ASME Code strength values for stainless steel nuclear piping (INEL ; INEL-95/00197; CONF-950740-102; DE96002047)
Paper図書
Ware, A.G.EG and G Idaho, Inc.1995.11.
Other Libraries in Japan
  • Author HeadingWare, A.G.

APPLICATION OF NUREG/CR-5999 INTERIM FATIGUE CURVES TO SELECTED NUCLEAR POWER PLANT COMPONENTS. (NUREG ; NUREG/CR-6260)

APPLICATION OF NUREG/CR-5999 INTERIM FATIGUE CURVES TO SELECTED NUCLEAR POWER PLANT COMPONENTS. (NUREG ; NUREG/CR-6260)
Paper図書
WARE, A.G.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1995.
Other Libraries in Japan
  • Author HeadingWARE, A.G.

Application of environmentally-corrected fatigue curves to nuclear power plant components (INEL ; INEL-96/00105; CONF-960706-10; DE96009012)

Application of environmentally-corrected fatigue curves to nuclear power plant components (INEL ; INEL-96/00105; CONF-960706-10; DE96009012)
Paper図書
Ware, A.G., Morton, D.K., Nitzel, M.E.Lockheed Idaho Technologies Co.1996.
Other Libraries in Japan
  • Author HeadingWare, A.G. Morton, D.K. Nitzel, M.E.

COMPONENT EVALUATION FOR INTERSYSTEM LOSS-OF-COOLANT ACCIDENTS IN ADVANCED LIGHT WATER REACTORS. (NUREG ; NUREG/CR-6121)

COMPONENT EVALUATION FOR INTERSYSTEM LOSS-OF-COOLANT ACCIDENTS IN ADVANCED LIGHT WATER REACTORS. (NUREG ; NUREG/CR-6121)
Paper図書
WARE, A.G.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1994.
Other Libraries in Japan
  • Author HeadingWARE, A.G.

PRELIMINARY EVALUATION OF SNUBBER SINGLE FAILURES. (NUREG ; NUREG/CR-6027)

PRELIMINARY EVALUATION OF SNUBBER SINGLE FAILURES. (NUREG ; NUREG/CR-6027)
Paper図書
WARE, A.G.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1993.
Other Libraries in Japan
  • Author HeadingWARE, A.G.

PROBABILISTIC BASED DESIGN RULES FOR INTERSYSTEM LOCAS IN ABWR PIPING. (EGG ; EGG-M-92638)

PROBABILISTIC BASED DESIGN RULES FOR INTERSYSTEM LOCAS IN ABWR PIPING. (EGG ; EGG-M-92638)
Paper図書
WARE, A.G.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1993.
Other Libraries in Japan
  • Author HeadingWARE, A.G.

Effects on fatigue life of gate valves due to higher torque switch settings during operability testing (INEL ; INEL-95/0557; DE96004130)

Effects on fatigue life of gate valves due to higher torque switch settings during operability testing (INEL ; INEL-95/0557; DE96004130)
Paper図書
Richins, W.D., Snow, S.D., Miller, G.K. [et al.]Lockheed Idaho Technologies Co.1995.12.
Other Libraries in Japan
  • Author HeadingRichins, W.D. Snow, S.D. Miller, G.K. Russell, M.J. Ware, A.G.

THREE TECHNICAL ISSUES IN FATIGUE DAMAGE ASSESSMENT OF NUCLEAR POWER PLANT COMPONENTS. (EGG ; EGG-M-91047)

THREE TECHNICAL ISSUES IN FATIGUE DAMAGE ASSESSMENT OF NUCLEAR POWER PLANT COMPONENTS. (EGG ; EGG-M-91047)
Paper図書
WARE, A.G.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1991.
Other Libraries in Japan
  • Author HeadingWARE, A.G.

SURVEY OF FATIGUE MONITORING IN THE NUCLEAR POWER INDUSTRY. (EGG ; EGG-M-91449)

SURVEY OF FATIGUE MONITORING IN THE NUCLEAR POWER INDUSTRY. (EGG ; EGG-M-91449)
Paper図書
WARE, A.G.EG and G Idaho, Inc.(EG and G Idaho, Inc.)1991.
Other Libraries in Japan
  • Author HeadingWARE, A.G.

Technical evaluation of Generic Issue 113: Dynamic qualification and testing of large bore hydraulic snubbers (NUREG ; NUREG/CR-5416) (EGG ; EGG-2571)

Technical evaluation of Generic Issue 113: Dynamic qualification and testing of large bore hydraulic snubbers (NUREG ; NUREG/CR-5416) (EGG ; EGG-2571)
Paper図書
M.E. Nitzel, A.G. Ware, J.D. Page1992
Other Libraries in Japan
  • Author HeadingNitzel, M.E. Ware, A.G. Page, J.D.

MECHANICAL DAMAGE EXPERIENCE IN MAJOR LIGHT WATER REACTOR SYSTEMS. (EGG ; EGG-M-89412)

MECHANICAL DAMAGE EXPERIENCE IN MAJOR LIGHT WATER REACTOR SYSTEMS. (EGG ; EGG-M-89412)
Paper図書
WARE, A.G.EG and G Idaho, Inc.(EG and G Idaho, Inc.)1990.
Other Libraries in Japan
  • Author HeadingWARE, A.G.
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