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Search results 18

RISK ASSESSMENT OF ISOLATION DEVICES IN SAFETY SYSTEMS. (NUREG ; NUREG/CR-5863)

RISK ASSESSMENT OF ISOLATION DEVICES IN SAFETY SYSTEMS. (NUREG ; NUREG/CR-5863)
Paper図書
CRAMOND, W.R.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1993.
Other Libraries in Japan
  • Author HeadingCRAMOND, W.R.

LOSS OF ESSENTIAL SERVICE WATER IN LWRS (GI-153). (NUREG ; NUREG/CR-5910)

LOSS OF ESSENTIAL SERVICE WATER IN LWRS (GI-153). (NUREG ; NUREG/CR-5910)
Paper図書
CRAMOND, W.R.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1992.
Other Libraries in Japan
  • Author HeadingCRAMOND, W.R.

An evaluation of internal event level 1 PRA methods used in NUREG-1150 (SAND ; SAND-88-1455C; CONF-890405-12; DE89005232)

An evaluation of internal event level 1 PRA methods used in NUREG-1150 (SAND ; SAND-88-1455C; CONF-890405-12; DE89005232)
Paper図書
Camp, A.L., Cramond, W.R.Sandia National Labs.1989.1.
Other Libraries in Japan
  • Author HeadingCamp, A.L. Cramond, W.R.

Characterization of the internal event frequencies for the final NUREG-1150 (SAND ; SAND-88-0011C; CONF-880601-7; DE88004692)

Characterization of the internal event frequencies for the final NUREG-1150 (SAND ; SAND-88-0011C; CONF-880601-7; DE88004692)
Paper図書
Camp, A.L., Cramond, W.R.Sandia National Lab.1988.6.30.
Other Libraries in Japan
  • Author HeadingCamp, A.L. Cramond, W.R.

SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF A BABCOCK AND WILCOX PRESSURIZED WATER REACTOR: CASE STUDY. (NUREG ; NUREG-CR-4713)

SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF A BABCOCK AND WILCOX PRESSURIZED WATER REACTOR: CASE STUDY. (NUREG ; NUREG-CR-4713)
Paper図書
CRAMOND, W.R.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1987.
Other Libraries in Japan
  • Author HeadingCRAMOND, W.R.

Generic and plant specific applicability of recent NRC-sponsored level 1 PRAs (SAND ; SAND-88-1436C; CONF-890405-14; DE89005205)

Generic and plant specific applicability of recent NRC-sponsored level 1 PRAs (SAND ; SAND-88-1436C; CONF-890405-14; DE89005205)
Paper図書
Cramond, W.R.Sandia National Labs.1988.1.
Other Libraries in Japan
  • Author HeadingCramond, W.R.

SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF A COMBUSTION ENGINEERING 2-LOOP PRESSURIZED WATER REACTOR: CASE STUDY. (NUREG ; NUREG-CR-4710)

SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF A COMBUSTION ENGINEERING 2-LOOP PRESSURIZED WATER REACTOR: CASE STUDY. (NUREG ; NUREG-CR-4710)
Paper図書
CRAMOND, W.R.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1987.
Other Libraries in Japan
  • Author HeadingCRAMOND, W.R.

The role of NUREG-1150 in accident management (SAND ; SAND-88-1445C; CONF-881011-1; DE88011203)

The role of NUREG-1150 in accident management (SAND ; SAND-88-1445C; CONF-881011-1; DE88011203)
Paper図書
Camp, A.L., Cramond, W.R., Sype, T.T.Sandia National Labs.1988.1.
Other Libraries in Japan
  • Author HeadingCamp, A.L. Cramond, W.R. Sype, T.T.

SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF A WESTINGHOUSE 2-LOOP PRESSURIZED WATER REACTOR: CASE STUDY. (NUREG ; NUREG-CR-4458)

SHUTDOWN DECAY HEAT REMOVAL ANALYSIS OF A WESTINGHOUSE 2-LOOP PRESSURIZED WATER REACTOR: CASE STUDY. (NUREG ; NUREG-CR-4458)
Paper図書
CRAMOND, W.R.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1987.
Other Libraries in Japan
  • Author HeadingCRAMOND, W.R.

Improvements to the original NUREG-1150 accident sequence analyses (SAND ; SAND-87-1898C; CONF-8710111-1; DE88001653)

Improvements to the original NUREG-1150 accident sequence analyses (SAND ; SAND-87-1898C; CONF-8710111-1; DE88001653)
Paper図書
Cramond, W.R., Camp, A.L.Sandia National Labs.1987.1.
Other Libraries in Japan
  • Author HeadingCramond, W.R. Camp, A.L.

Shutdown decay heat removal analysis of a Babcock and Wilcox pressurized water reactor: Case study (SAND ; SAND-86-1832)

Shutdown decay heat removal analysis of a Babcock and Wilcox pressurized water reactor: Case study (SAND ; SAND-86-1832)
Paper図書
Sandia National Laboratories(Sandia National Laboratories)1987.
Other Libraries in Japan
  • Author HeadingCramond, W.R. Ericson, D.M. Jr. Sanders, G....

Shutdown decay heat removal analysis of a Combustion Engineering 2-loop pressurized water reactor: Case study (SAND ; SAND-86-1797)

Shutdown decay heat removal analysis of a Combustion Engineering 2-loop pressurized water reactor: Case study (SAND ; SAND-86-1797)
Paper図書
Sandia National Laboratories(Sandia National Laboratories)1987.
Other Libraries in Japan
  • Author HeadingCramond, W.R. Ericson, D.M. Jr. Sanders, G....

Shutdown decay heat removal analysis of a Westinghouse 2-loop pressurized water reactor: Case study (SAND ; SAND-86-2496)

Shutdown decay heat removal analysis of a Westinghouse 2-loop pressurized water reactor: Case study (SAND ; SAND-86-2496)
Paper図書
Sandia National Laboratories(Sandia National Laboratories)1987.
Other Libraries in Japan
  • Author HeadingCramond, W.R. Ericson, D.M. Jr. Sanders, G....

Shutdown Decay Heat Removal analysis of a Westinghouse 3-loop pressurized water reactor: Case study (SAND ; SAND-86-2377)

Shutdown Decay Heat Removal analysis of a Westinghouse 3-loop pressurized water reactor: Case study (SAND ; SAND-86-2377)
Paper図書
Sandia National Laboratories(Sandia National Laboratories)1987.
Other Libraries in Japan
  • Author HeadingCramond, W.R. Ericson, D.M. Jr. Sanders, G....

Probabilistic risk assessment course documentation. Volume 2. Probability and statistics for PRA applications (SAND ; SAND--85-1495/2)

Probabilistic risk assessment course documentation. Volume 2. Probability and statistics for PRA applications (SAND ; SAND--85-1495/2)
Paper図書
Sandia National Laboratories(Sandia National Laboratories)1985.
Other Libraries in Japan
  • Author HeadingCramond, W.R. Iman, R.L. Prairie, R.R.

SIMPLIFIED SEISMIC RISK METHODOLOGY APPLIED TO GENERIC SHUTDOWN HEAT REMOVAL ISSUES FOR US REACTORS (CONF ; CONF-850809--6)

SIMPLIFIED SEISMIC RISK METHODOLOGY APPLIED TO GENERIC SHUTDOWN HEAT REMOVAL ISSUES FOR US REACTORS (CONF ; CONF-850809--6)
Paper図書
1985.
Other Libraries in Japan

ANALYSIS OF NUCLEAR POWER PLANT SYSTEMS CONTAINING RADIOACTIVITY IN A CORE DAMAGE ACCIDENT. (NUREG ; NUREG-CR-2270; SAND-80-2838)

ANALYSIS OF NUCLEAR POWER PLANT SYSTEMS CONTAINING RADIOACTIVITY IN A CORE DAMAGE ACCIDENT. (NUREG ; NUREG-CR-2270; SAND-80-2838)
Paper図書
CRAMOND, W.R.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1981.
Other Libraries in Japan
  • Author HeadingCRAMOND, W.R.

Systems interaction methodology applications program. Final report on Phase 1 (NUREG ; NUREG/CR-1321) (SAND ; SAND-80-0384)

Systems interaction methodology applications program. Final report on Phase 1 (NUREG ; NUREG/CR-1321) (SAND ; SAND-80-0384)
Paper図書
G.J. Boyd [et al.]1980
Other Libraries in Japan
  • Author HeadingBoyd, G.J. Cramond, W.R. Hatch, S.W. Hickman, J.W. Kol...

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