PARET; water-cooled core transient analysis. [IBM360,370,303x; FORTRAN IV (90) and BAL (10)]
Technical Report
·
OSTI ID:6400941
This program is designed for use in predicting the course and consequences of nondestructive reactivity accidents in small reactor cores.IBM360,370,303x; FORTRAN IV (90%) and BAL (10%); OS/360; 240K bytes plus one magnetic tape.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- OSTI ID:
- 6400941
- Report Number(s):
- ANL/NESC-555; ON: DE83048555
- Country of Publication:
- United States
- Language:
- English
Similar Records
6KILER; core heatup code for BWR/6 analysis. [IBM360,370/195; FORTRAN IV (95%) and BAL (5%)]
SCORE3; SCISRS ENDF/B graphic cross section evaluation. [IBM360; FORTRAN IV and BAL]
VIM1; VIM1X; Monte Carlo critical assembly analysis. [CDC7600; IBM360; FORTRAN IV (CDC7600), FORTRAN IV and BAL (IBM360)]
Technical Report
·
·
OSTI ID:6400935
SCORE3; SCISRS ENDF/B graphic cross section evaluation. [IBM360; FORTRAN IV and BAL]
Technical Report
·
·
OSTI ID:6365152
VIM1; VIM1X; Monte Carlo critical assembly analysis. [CDC7600; IBM360; FORTRAN IV (CDC7600), FORTRAN IV and BAL (IBM360)]
Technical Report
·
·
OSTI ID:6392196
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
C CODES
COMPUTER CODES
ENERGY TRANSFER
FEEDBACK
FLUID MECHANICS
FORTRAN
HEAT TRANSFER
HYDRODYNAMICS
MECHANICS
P CODES
PROGRAMMING LANGUAGES
REACTIVITY
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
TRANSIENTS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
C CODES
COMPUTER CODES
ENERGY TRANSFER
FEEDBACK
FLUID MECHANICS
FORTRAN
HEAT TRANSFER
HYDRODYNAMICS
MECHANICS
P CODES
PROGRAMMING LANGUAGES
REACTIVITY
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
TRANSIENTS