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DAMAGED FUEL EXPERIMENT DF-1. (NUREG ; NUREG-CR-4668)

DAMAGED FUEL EXPERIMENT DF-1. (NUREG ; NUREG-CR-4668)
Paper図書
GASSER, R.D.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1990.
Other Libraries in Japan
  • Author HeadingGASSER, R.D.

Results and phenomena observed from the DF-4 BWR (boiling water reactor) control blade-channel box test (SAND ; SAND-88-0581; CONF-881014-13; DE89001377)

Results and phenomena observed from the DF-4 BWR (boiling water reactor) control blade-channel box test (SAND ; SAND-88-0581; CONF-881014-13; DE89001377)
Paper図書
Gauntt, R.O., Gasser, R.D., Fryer, C.P. [et al.]Sandia National Labs.1988.1.
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  • Author HeadingGauntt, R.O. Gasser, R.D. Fryer, C.P. Walker, J.V.

RESULTS OF THE DF-4 BWR (BOILING WATER REACTOR) CONTROL BLADECHANNEL BOX TEST (SAND ; SAND-90-2716C)

RESULTS OF THE DF-4 BWR (BOILING WATER REACTOR) CONTROL BLADECHANNEL BOX TEST (SAND ; SAND-90-2716C)
Paper図書
GAUNTT, R.O.// GASSER, R.D. (SANDIA NATIONAL LABS., ALBUQUERQUE, NM (USA))Sandia National Laboratories(Sandia National Laboratories)1990.
Other Libraries in Japan
  • Author HeadingGAUNTT, R.O. GASSER, R.D.

DEBRIS MODULE: AN EFFECTIVE TOOL FOR THE ANALYSIS OF MELT PROGRESSION IN LWRS (LIGHT WATER REACTORS) (SAND ; SAND-90-2712C)

DEBRIS MODULE: AN EFFECTIVE TOOL FOR THE ANALYSIS OF MELT PROGRESSION IN LWRS (LIGHT WATER REACTORS) (SAND ; SAND-90-2712C)
Paper図書
GASSER, R.D.// DOSANJH, S.S.// GAUNTT, R.O. (SANDIA NATIONAL LABS., ALBUQUERQUE, NM (USA))Sandia National Laboratories(Sandia National Laboratories)1990.
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  • Author HeadingGASSER, R.D. DOSANJH, S.S. GAUNTT, R.O.

Calculations of containment loading due to high pressure ejection of core debris (Sandia report ; SAND-86-2464C; CONF-8610135-29; DE87001736)

Calculations of containment loading due to high pressure ejection of core debris (Sandia report ; SAND-86-2464C; CONF-8610135-29; DE87001736)
Paper図書
Gasser, R.D. Carroll, D.E.Sandia National Labs.1986.01.
Other Libraries in Japan
  • Author HeadingGasser, R.D. Carroll, D.E.

ANALYSIS OF STATION BLACKOUT ACCIDENTS FOR THE BELLEFONTE PRESSURIZED WATER REACTOR (NUREG ; NUREG/CR-4563; SAND-86-0576)

ANALYSIS OF STATION BLACKOUT ACCIDENTS FOR THE BELLEFONTE PRESSURIZED WATER REACTOR (NUREG ; NUREG/CR-4563; SAND-86-0576)
Paper図書
GASSER, R.D./BIENIARZ, P.P.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1986.
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  • Author HeadingGASSER, R.D. BIENIARZ, P.P.

Containment response and radiological release for a TMLB' accident sequence in a large dry containment (Sandia report ; SAND-86-1071C; CONF-860507-1; TI86010474)

Containment response and radiological release for a TMLB' accident sequence in a large dry containment (Sandia report ; SAND-86-1071C; CONF-860507-1; TI86010474)
Paper図書
Gasser, R.D., Bieniarz, P.P., Tills, J.L.Sandia National Labs., Risk Management Associates, Tills (Jack) and Associates, Inc.1986.01.
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  • Author HeadingGasser, R.D. Bieniarz, P.P. Tills, J.L.

THERMAL RESPONSE OF A MOLTEN POOL WITH STEFAN TYPE BOUNDARY CONDITIONS. (BNL ; BNL-NUREG-27197)

THERMAL RESPONSE OF A MOLTEN POOL WITH STEFAN TYPE BOUNDARY CONDITIONS. (BNL ; BNL-NUREG-27197)
Paper図書
GASSER, R.D.(et al.)Brookhaven National Laboratory(Brookhaven National Laboratory)1980.
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  • Author HeadingGASSER, R.D.

CONAN; AN LMFBR CONTAINMENT RESPONSE COMPUTER CODE. (NUREG ; NUREG/CR-1355; BNL-NUREG-51151)

CONAN; AN LMFBR CONTAINMENT RESPONSE COMPUTER CODE. (NUREG ; NUREG/CR-1355; BNL-NUREG-51151)
Paper図書
Gasser, R.D.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1979.
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  • Author HeadingGasser, R.D.

CONTAINMENT RESPONSE TO POSTULATED CORE MELTDOWN ACCIDENTS IN THE FAST FLUX TEST FACILITY. (BNL ; BNL-NUREG-24141-R)

CONTAINMENT RESPONSE TO POSTULATED CORE MELTDOWN ACCIDENTS IN THE FAST FLUX TEST FACILITY. (BNL ; BNL-NUREG-24141-R)
Paper図書
GASSER, R.D.(et al.)Brookhaven National Laboratory(Brookhaven National Laboratory)1978.
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  • Author HeadingGASSER, R.D.

Containment response to postulated ex-vessel core meltdown accidents in the fast flux test facility (BNL ; BNL-NUREG-25522) (CONF ; CONF-790816-1)

Containment response to postulated ex-vessel core meltdown accidents in the fast flux test facility (BNL ; BNL-NUREG-25522) (CONF ; CONF-790816-1)
Paper図書
W.T. Pratt, R.D. Gasser, A.R. Marchese1979
Other Libraries in Japan
  • Author HeadingPratt, W.T. Gasser, R.D. Marchese, A.R.

POST ACCIDENT HEAT REMOVAL WITH ADVANCED LMFBR FUELS. (UCLA ; UCLA-ENG-7518)

POST ACCIDENT HEAT REMOVAL WITH ADVANCED LMFBR FUELS. (UCLA ; UCLA-ENG-7518)
Paper図書
GASSER, R.D.
Other Libraries in Japan
  • Author HeadingGASSER, R.D.

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