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TRAC (TRANSIENT REACTOR ANALYSIS CODE)-PF1/MOD1 CORRELATIONS AND MODELS. (INFORMAL REPT.) (NUREG ; NUREG/CR-5069; LA-11208-MS)

TRAC (TRANSIENT REACTOR ANALYSIS CODE)-PF1/MOD1 CORRELATIONS AND MODELS. (INFORMAL REPT.) (NUREG ; NUREG/CR-5069; LA-11208-MS)
Paper図書
LILES, D.R.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1988.
Other Libraries in Japan

TRAC-PF1: An advanced best-estimate computer program for pressurized water reactor analysis. (NUREG ; NUREG/CR-3567; LA-9944-MS)

TRAC-PF1: An advanced best-estimate computer program for pressurized water reactor analysis. (NUREG ; NUREG/CR-3567; LA-9944-MS)
Paper図書
Liles, D.R./Mahaffy, J.H.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1984.
Other Libraries in Japan

APPROACH TO FLUID-MECHANICS CALCULATIONS ON SERIAL AND PARALLEL COMPUTER ARCHITECTURES. (LA ; LA-UR-83-1881)

APPROACH TO FLUID-MECHANICS CALCULATIONS ON SERIAL AND PARALLEL COMPUTER ARCHITECTURES. (LA ; LA-UR-83-1881)
Paper図書
LILES, D.R.(et al.)1983.
Other Libraries in Japan

TRAC-PF1/MOD1 COMPUTER CODE. (LA ; LA-UR-83-2396)

TRAC-PF1/MOD1 COMPUTER CODE. (LA ; LA-UR-83-2396)
Paper図書
LILES, D.R.(et al.)1983.
Other Libraries in Japan

CURRENT ALGORITHMS USED IN REACTOR SAFETY CODES AND THE IMPACT OF FUTURE COMPUTER DEVELOPMENT ON THESE ALGORITHMS (CONF ; CONF-850646-2)

CURRENT ALGORITHMS USED IN REACTOR SAFETY CODES AND THE IMPACT OF FUTURE COMPUTER DEVELOPMENT ON THESE ALGORITHMS (CONF ; CONF-850646-2)
Paper図書
1985.
Other Libraries in Japan
  • Author HeadingMahaffy, J H Liles, D R Woodruff, S B

TRAC-PF1/MOD1 COMPUTER CODE (CONF ; CONF-8410142-24)

TRAC-PF1/MOD1 COMPUTER CODE (CONF ; CONF-8410142-24)
Paper図書
1984.
Other Libraries in Japan
  • Author HeadingLiles, D R Mahaffy, J H

TRAC-PF1/MOD1 COMPUTER CODE. [PWR] (CONF ; CONF-830901-7)

TRAC-PF1/MOD1 COMPUTER CODE. [PWR] (CONF ; CONF-830901-7)
Paper図書
1983.
Other Libraries in Japan
  • Author HeadingLiles, D R Mahaffy, J H

FLOW REGIMES. (LA ; LA-UR-82-1291)

FLOW REGIMES. (LA ; LA-UR-82-1291)
Paper図書
LILES, D.R.1982.
Other Libraries in Japan

LOS ALAMOS NUCLEAR PLANT ANALYZER: AN INTERACTIVE POWER-PLANT SIMULATION PROGRAM (CONF ; CONF-8410142-18)

LOS ALAMOS NUCLEAR PLANT ANALYZER: AN INTERACTIVE POWER-PLANT SIMULATION PROGRAM (CONF ; CONF-8410142-18)
Paper図書
1984.
Other Libraries in Japan
  • Author HeadingSteinke, R Booker, C Giguere, P Liles, D R Mahaffy, J H Turner, M R

MODELING OF LARGE PRESSURIZED WATER REACTORS. (LA ; LA-UR-79-483)

MODELING OF LARGE PRESSURIZED WATER REACTORS. (LA ; LA-UR-79-483)
Paper図書
LILES, D.R.(et al.)1979.
Other Libraries in Japan

THREE DIMENSIONAL TWO FLUID NUMERICAL TREATMENT OF A REACTOR VESSEL IN TRAC. (LA ; LA-UR-79-59)

THREE DIMENSIONAL TWO FLUID NUMERICAL TREATMENT OF A REACTOR VESSEL IN TRAC. (LA ; LA-UR-79-59)
Paper図書
LILES, D.R.1979.
Other Libraries in Japan

POST: a postprocessor computer code for producing three-dimensional movies of two-phase flow in a reactor vessel (LA ; LA-NUREG-6954-MS)

POST: a postprocessor computer code for producing three-dimensional movies of two-phase flow in a reactor vessel (LA ; LA-NUREG-6954-MS)
Paper図書
K.A. Taggart, D.R. LilesLos Alamos Scientific Lab.1977.8.
Other Libraries in Japan

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