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FORCED CONVECTIVE, NONEQUILIBRIUM. (NUREG ; NUREG/CR-3193; EGG-2245)

FORCED CONVECTIVE, NONEQUILIBRIUM. (NUREG ; NUREG/CR-3193; EGG-2245)
Paper図書
GOTTULA, R.C.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1985.
Other Libraries in Japan
  • Author HeadingGOTTULA, R.C.

Forced convective, nonequilibrium, post-CHF heat transfer experiment data and correation comparicon report. (NUREG ; NUREG/CR-3193; EGG-2245)

Forced convective, nonequilibrium, post-CHF heat transfer experiment data and correation comparicon report. (NUREG ; NUREG/CR-3193; EGG-2245)
Paper図書
Gottula, R.C./Condie, K.G./and othersNUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1985.
Other Libraries in Japan
  • Author HeadingGottula, R.C. Condie, K.G. and others

Effects of cladding sorface thermocouples and electrical heater rod desigh on quench behavior. (NUREG ; NUREG/CR-2691; EGG-2186)

Effects of cladding sorface thermocouples and electrical heater rod desigh on quench behavior. (NUREG ; NUREG/CR-2691; EGG-2186)
Paper図書
Gottula, R.C.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1984.
Other Libraries in Japan
  • Author HeadingGottula, R.C.

EFFECTS OF CLADDING EXTERNAL THERMOCOUPLES AND ELECTRICAL-HEATER-ROD DESIGN ON QUENCH BEHAVIOR. (EGG ; EGG-M-06982)

EFFECTS OF CLADDING EXTERNAL THERMOCOUPLES AND ELECTRICAL-HEATER-ROD DESIGN ON QUENCH BEHAVIOR. (EGG ; EGG-M-06982)
Paper図書
GOTTULA, R.C.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1983.
Other Libraries in Japan
  • Author HeadingGOTTULA, R.C.

FORCED-CONVECTIVE NONEQUILIBRIUM POST-CHF HEAT-TRANSFER EXPERIMENTS IN A VERTICAL TUBE. (EGG ; EGG-M-13782)

FORCED-CONVECTIVE NONEQUILIBRIUM POST-CHF HEAT-TRANSFER EXPERIMENTS IN A VERTICAL TUBE. (EGG ; EGG-M-13782)
Paper図書
GOTTULA, R.C.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1983.
Other Libraries in Japan
  • Author HeadingGOTTULA, R.C.

Severe Accident Sequence Analysis Program: Anticipated transient without scram simulations for Browns Ferry Nuclear Plant Unit 1 (NUREG ; NUREG/CR-4165) (EGG ; EGG-2379)

Severe Accident Sequence Analysis Program: Anticipated transient without scram simulations for Browns Ferry Nuclear Plant Unit 1 (NUREG ; NUREG/CR-4165) (EGG ; EGG-2379)
Paper図書
R.J. Dallman [et al.]EG and G Idaho, Inc.1987.5.
Other Libraries in Japan
  • Author HeadingDallman, R.J. Gottula, R.C. Holcomb, E.E. Jouse, W.C. Wag...

EFFECTS OF CLADDING SURFACE THERMOCOUPLES AND ELECTRICAL HEATER ROD DESIGN ON QUENCH BEHAVIOR. (NUREG ; NUREG-CR-2691)

EFFECTS OF CLADDING SURFACE THERMOCOUPLES AND ELECTRICAL HEATER ROD DESIGN ON QUENCH BEHAVIOR. (NUREG ; NUREG-CR-2691)
Paper図書
GOTTULA, R.C.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1984.
Other Libraries in Japan
  • Author HeadingGOTTULA, R.C.

FORCED CONVECTIVE, NONEQUILIBRIUM POST-CHF HEAT TRANSFER EXPERIMENT: DESCRIPTION, DATA ANALYSIS AND CORRELATION COMPARISON (CONF ; CONF-8404146-2)

FORCED CONVECTIVE, NONEQUILIBRIUM POST-CHF HEAT TRANSFER EXPERIMENT: DESCRIPTION, DATA ANALYSIS AND CORRELATION COMPARISON (CONF ; CONF-8404146-2)
Paper図書
1984.
Other Libraries in Japan

COMPARISON OF HEAT AND MASS TRANSFER CORRELATIONS WITH FORCED CONVECTIVE MONEQUILIBRIUM POST-CHF EXPERIMENTAL DATA (CONF ; CONF-840816-19)

COMPARISON OF HEAT AND MASS TRANSFER CORRELATIONS WITH FORCED CONVECTIVE MONEQUILIBRIUM POST-CHF EXPERIMENTAL DATA (CONF ; CONF-840816-19)
Paper図書
1984.
Other Libraries in Japan

EFFECT OF CLADDING SURFACE THERMOCOUPLES ON THE QUENCH BEHAVIOR OF AN ELECTRICAL HEATER ROD. (EGG ; EGG-LTR-LO-00-80-115)

EFFECT OF CLADDING SURFACE THERMOCOUPLES ON THE QUENCH BEHAVIOR OF AN ELECTRICAL HEATER ROD. (EGG ; EGG-LTR-LO-00-80-115)
Paper図書
GOTTULA, R.C.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1980.
Other Libraries in Japan
  • Author HeadingGOTTULA, R.C.

ASSESSMENT OF LOFT FUEL ROD QUENCH BEHAVIOR BASED ON ELECTRIC ROD QUENCH TESTS. (CONF ; CONF-801091-4)

ASSESSMENT OF LOFT FUEL ROD QUENCH BEHAVIOR BASED ON ELECTRIC ROD QUENCH TESTS. (CONF ; CONF-801091-4)
Paper図書
GOTTULA, R.C.(et al.)1980.
Other Libraries in Japan
  • Author HeadingGOTTULA, R.C.

Rev 0 to EMF-2145, "Millstone Unit 2 Large Break LOCA/ECCS Analysis With Replacement SGs & Plant Modifications."

Rev 0 to EMF-2145, "Millstone Unit 2 Large Break LOCA/ECCS Analysis With Replacement SGs & Plant Modifications."
Paper図書
GOTTULA, R. C.//HOLM, J. S.//SHAW, R. A.SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER1998/11/30.
Other Libraries in Japan

Rev 0 to EMF-2079, "Millstone Unit 2 Large Break LOCA/ECCS Analysis With Replacement SGs."

Rev 0 to EMF-2079, "Millstone Unit 2 Large Break LOCA/ECCS Analysis With Replacement SGs."
Paper図書
GOTTULA, R. C.//HOLM, J. S.//SHAW, R. A.SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER1998/09/30.
Other Libraries in Japan

EFFECT OF ROD SURFACE THERMOCOUPLES ON TRANSIENT CRITICAL HEAT FLUX. (INIS ; INIS-MF-4588)

EFFECT OF ROD SURFACE THERMOCOUPLES ON TRANSIENT CRITICAL HEAT FLUX. (INIS ; INIS-MF-4588)
Paper図書
GOTTULA, R.C.(et al.)International Atomic Energy Agency(International Atomic Energy Agency)1978.
Other Libraries in Japan
  • Author HeadingGOTTULA, R.C.

LOFT transient (blowdown) critical heat flux tests (NUREG ; NUREG/CR-0230; TREE-NUREG-1240)

LOFT transient (blowdown) critical heat flux tests (NUREG ; NUREG/CR-0230; TREE-NUREG-1240)
Paper図書
Gottula, R.C.Idaho National Engineering Lab.1978.04.
Other Libraries in Japan
  • Author HeadingGottula, R.C.

LOFT TRANSIENT (BLOWDOWN) CRITICAL HEAT FLUX TESTS. (TREE ; TREE-NUREG-1240, MUREG/CR-0230)

LOFT TRANSIENT (BLOWDOWN) CRITICAL HEAT FLUX TESTS. (TREE ; TREE-NUREG-1240, MUREG/CR-0230)
Paper図書
GOTTULA, R.C.1978.
Other Libraries in Japan
  • Author HeadingGOTTULA, R.C.

LOFT STEADY STATE CRITICAL HEAT FLUX TESTS (6.9 TO 13.8 MPA) (TREE ; TREE-NUREG-1166; NUREG/CR-0237)

LOFT STEADY STATE CRITICAL HEAT FLUX TESTS (6.9 TO 13.8 MPA) (TREE ; TREE-NUREG-1166; NUREG/CR-0237)
Paper図書
GOTTULA, R.C.1978.
Other Libraries in Japan
  • Author HeadingGOTTULA, R.C.

FLOW RATE CALCULATIONS FOR LOFT CORE SUPPORT BARREL OUTLET NOZZLE: REACTOR VESSEL OUTLET NOZZLE. (TID ; TID-27665)

FLOW RATE CALCULATIONS FOR LOFT CORE SUPPORT BARREL OUTLET NOZZLE: REACTOR VESSEL OUTLET NOZZLE. (TID ; TID-27665)
Paper図書
GOTTULA, R.C.1972.
Other Libraries in Japan
  • Author HeadingGOTTULA, R.C.

EFFECT OF ROD SURFACE THERMOCOUPLES ON TRANSIENT CRITICAL HEAT FLUX. (CONF ; CONF-781022-20)

EFFECT OF ROD SURFACE THERMOCOUPLES ON TRANSIENT CRITICAL HEAT FLUX. (CONF ; CONF-781022-20)
Paper図書
GOTTULA, R.C.
Other Libraries in Japan
  • Author HeadingGOTTULA, R.C.

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