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Risk evaluation for a General Electric BWR, effects of fire protection system actuation on safety-related equipment microform : evaluation of generic issue 57 / prepared by J. Lambright ... [et al.]

Risk evaluation for a General Electric BWR, effects of fire protection system actuation on safety-related equipment microform : evaluation of generic issue 57 / prepared by J. Lambright ... [et al.]
Microform図書
1992<YCA-Y 3.N 88:25/5791>
National Diet Library

Risk evaluation for a B&W pressurized water reactor, effects of fire protection system actuation on safety-related equipment microform : evaluation of generic issue 57 / prepared by J. Lambright ... [et al.]

Risk evaluation for a B&W pressurized water reactor, effects of fire protection system actuation on safety-related equipment microform : evaluation of generic issue 57 / prepared by J. Lambright ... [et al.]
Microform図書
1992<YCA-Y 3.N 88:25/5790>
National Diet Library

Risk evaluation for a Westinghouse PWR, effects of fire protection system actuation on safety-related equipment microform : evaluation of generic issue 57 / prepared by J. Lambright ... [et al.]

Risk evaluation for a Westinghouse PWR, effects of fire protection system actuation on safety-related equipment microform : evaluation of generic issue 57 / prepared by J. Lambright ... [et al.]
Microform図書
1992<YCA-Y 3.N 88:25/5789>
National Diet Library

EVALUATION OF GENERIC ISSUE 57: EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON SAFETY-RELATED EQUIPMENT. (NUREG ; NUREG/CR-5580-VOL.1)

EVALUATION OF GENERIC ISSUE 57: EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON SAFETY-RELATED EQUIPMENT. (NUREG ; NUREG/CR-5580-VOL.1)
Paper図書
LAMBRIGHT, J.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1992.
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  • Author HeadingLAMBRIGHT, J.

RISK EVALUATION FOR A WESTINGHOUSE PWR, EFFECTS OF FIRE PROTECTION SYSTEMS ACTUATION ON SAFETY-RELATED EQUIPMENT. (NUREG ; NUREG/CR-5789)

RISK EVALUATION FOR A WESTINGHOUSE PWR, EFFECTS OF FIRE PROTECTION SYSTEMS ACTUATION ON SAFETY-RELATED EQUIPMENT. (NUREG ; NUREG/CR-5789)
Paper図書
LAMBRIGHT, J.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1992.
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  • Author HeadingLAMBRIGHT, J.

RISK EVALUATION FOR A GENERAL ELECTRIC BWR, EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON SAFETY-RELATED EQUIPMENT. (NUREG ; NUREG/CR-5791)

RISK EVALUATION FOR A GENERAL ELECTRIC BWR, EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON SAFETY-RELATED EQUIPMENT. (NUREG ; NUREG/CR-5791)
Paper図書
LAMBRIGHT, J.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1992.
Other Libraries in Japan
  • Author HeadingLAMBRIGHT, J.

RISK EVALUATION FOR A B&W PRESSURIZED WATER REACTOR, EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON SAFETY-RELATED EQUIPMENT. (NUREG ; NUREG/CR-5790)

RISK EVALUATION FOR A B&W PRESSURIZED WATER REACTOR, EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON SAFETY-RELATED EQUIPMENT. (NUREG ; NUREG/CR-5790)
Paper図書
LAMBRIGHT, J.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1992.
Other Libraries in Japan
  • Author HeadingLAMBRIGHT, J.

Final rept, "Prairie Island Fire IPEEE Technical Assessment."

Final rept, "Prairie Island Fire IPEEE Technical Assessment."
Paper図書
LAMBRIGHT, J.//ZEE, K.ERIN ENGINEERING & RESEARCH, INC.1998/02/28.
Other Libraries in Japan
  • Author HeadingLAMBRIGHT, J.//ZEE, K.

Procedures for the external event core damage frequency analyses for NUREG-1150 / prepared by M.P. Bohn, J.A. Lambright

Procedures for the external event core damage frequency analyses for NUREG-1150 / prepared by M.P. Bohn, J.A. Lambright
Microform図書
1990<YCA-Y 3.N 88:25/4840>
National Diet Library
  • Author HeadingBohn, Michael P Lambright, J. A U.S. Nuclear Regulatory Com...

"Technical Evaluation Rept On Submittal - Only Review Of Individual Plant Exam Of External Events At Diablo Canyon Power Plant," final rept.

"Technical Evaluation Rept On Submittal - Only Review Of Individual Plant Exam Of External Events At Diablo Canyon Power Plant," final rept.
Paper図書
KHATIBRAHBAR, //LAMBRIGHT, J. A.//SEWELL, R.ENERGY RESEARCH, INC.1997/09/30.
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  • Author HeadingKHATIBRAHBAR, //LAMBRIGHT, J. A.//SEWELL, R.

ANALYSIS OF CORE DAMAGE FREQUENCY: PEACH BOTTOM, UNIT 2 EXTERNAL EVENTS. (NUREG ; NUREG-CR-4550-VOL.4-REV.1-PT.3)

ANALYSIS OF CORE DAMAGE FREQUENCY: PEACH BOTTOM, UNIT 2 EXTERNAL EVENTS. (NUREG ; NUREG-CR-4550-VOL.4-REV.1-PT.3)
Paper図書
LAMBRIGHT, J.A.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1990.
Other Libraries in Japan
  • Author HeadingLAMBRIGHT, J.A.

FIRE RISK SCOPING STUDY: INVESTIGATION OF NUCLEAR POWER PLANT FIRE RISK, INCLUDING PREVIOUSLY UNADDRESSED ISSUES. (TECHNICAL REPT.) (NUREG ; NUREG/CR-5088; SAND-88-0177)

FIRE RISK SCOPING STUDY: INVESTIGATION OF NUCLEAR POWER PLANT FIRE RISK, INCLUDING PREVIOUSLY UNADDRESSED ISSUES. (TECHNICAL REPT.) (NUREG ; NUREG/CR-5088; SAND-88-0177)
Paper図書
LAMBRIGHT, J.A.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1989.
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  • Author HeadingLAMBRIGHT, J.A.

ANALYSIS OF CORE DAMAGE FREQUENCY DUE TO FIRE AT THE SAVANNAH RIVER K-REACTOR (SAND ; SAND-89-1786)

ANALYSIS OF CORE DAMAGE FREQUENCY DUE TO FIRE AT THE SAVANNAH RIVER K-REACTOR (SAND ; SAND-89-1786)
Paper図書
LAMBRIGHT, J.A.// DANIEL, S.L.// BROSSEAU, D. (SANDIA NATIONAL LABS., ALBUQUERQUE, NM (USA))Sandia National Laboratories(Sandia National Laboratories)1991.
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  • Author HeadingLAMBRIGHT, J.A. DANIEL, S.L. BROSSEAU, D.

Observations concerning the COMPBRN III fire growth code (SAND ; SAND-88-2160C; CONF-890405-17; DE89005334)

Observations concerning the COMPBRN III fire growth code (SAND ; SAND-88-2160C; CONF-890405-17; DE89005334)
Paper図書
Nicolette, V.F., Nowlen, S.P., Lambright, J.A.Sandia National Labs.1989.1.
Other Libraries in Japan
  • Author HeadingNicolette, V.F. Nowlen, S.P. Lambright, J.A.

The impact of updated information and modeling techniques on four previously completed commercial nuclear power plant fire probabilistic risk assessments (SAND ; SAND-88-3355C; CONF-890405-8; DE89004580)

The impact of updated information and modeling techniques on four previously completed commercial nuclear power plant fire probabilistic risk assessments (SAND ; SAND-88-3355C; CONF-890405-8; DE89004580)
Paper図書
Lambright, J.A., Nowlen, S.P., Nicolette, V.F. [et al.]Sandia National Lab.1989.1.
Other Libraries in Japan
  • Author HeadingLambright, J.A. Nowlen, S.P. Nicolette, V.F...

An overview of the fire risk scoping study objectives, approach, findings and follow-on efforts (SAND ; SAND-88-3353C; CONF-890405-18; DE89005212)

An overview of the fire risk scoping study objectives, approach, findings and follow-on efforts (SAND ; SAND-88-3353C; CONF-890405-18; DE89005212)
Paper図書
Nowlen, S.P., Lambright, J.A., Nicolette, V.F. [et al.]Sandia National Lab.1989.1.
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  • Author HeadingNowlen, S.P. Lambright, J.A. Nicolette, V.F. Bohn, M.P.

DISCUSSION OF FIRE SUPPRESSION INDUCED EQUIPMENT DAMAGE AND SYSTEMS IMPACT THROUGH AN EXAMINATION OF SPURIOUS FIRE SUPPRESSION ACTUATION INCIDENTS (SAND ; SAND-89-1956C)

DISCUSSION OF FIRE SUPPRESSION INDUCED EQUIPMENT DAMAGE AND SYSTEMS IMPACT THROUGH AN EXAMINATION OF SPURIOUS FIRE SUPPRESSION ACTUATION INCIDENTS (SAND ; SAND-89-1956C)
Paper図書
NOWLEN, S.P.//LAMBRIGHT, J.A.// ROMIG, J.C. (SANDIA NATIONAL LABS., ALBUQUERQUE, NM (USA))Sandia National Laboratories(Sandia National Laboratories)1989.
Other Libraries in Japan
  • Author HeadingNOWLEN, S.P. LAMBRIGHT, J.A. ROMIG, J.C.

Summary of core damage frequency from internal initiators: Peach Bottom (Sandia report ; SAND-86-1567C; CONF-861102-12; TI86013310)

Summary of core damage frequency from internal initiators: Peach Bottom (Sandia report ; SAND-86-1567C; CONF-861102-12; TI86013310)
Paper図書
Kolaczkowski, A.M., Lambright, J.A., Cathey, N.Sandia National Labs., Idaho National Engineering Lab., Science Applications International Corp.1986.01.
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  • Author HeadingKolaczkowski, A.M. Lambright, J.A. Cathey, N.

ANALYSIS OF CORE DAMAGE FREQUENCY DUE TO EXTERNAL EVENTS AT THE DOE (DEPARTMENT OF ENERGY) N-REACTOR (SAND ; SAND-89-1147)

ANALYSIS OF CORE DAMAGE FREQUENCY DUE TO EXTERNAL EVENTS AT THE DOE (DEPARTMENT OF ENERGY) N-REACTOR (SAND ; SAND-89-1147)
Paper図書
LAMBRIGHT, J.A.// BOHN, M.P.// DANIEL, S.L.// BAXTER, J.T.// JOHNSON, J.J.// RAVINDRA, M.K.// HASHIMOTO, P.O.// MRAZ, M.J.// TONG, W.H.// CONOSCENTE, J.P. (SANDIA NATIONAL LABS., ALBUQUERQUE, NM (USA)// WESTINGHOUSE HANFORD CO., RICHLAND, WA (USA))Sandia National Laboratories(Sandia National Laboratories)1990.
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  • Author HeadingLAMBRIGHT, J.A. BOHN, M.P. DANIEL, S.L. BAX...

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