MOXY/MOD032; BWR core heat transfer code. [IBM360; CDC7600; FORTRAN IV and Assembly language (IBM360), FORTRAN IV and COMPASS (CDC7600)]
MOXY is used for the thermal analysis of a planar section of a boiling water reactor (BWR) fuel element during a loss-of-coolant accident (LOCA). The code employs models that describe heat transfer by conduction, convection, and thermal radiation, and heat generation by metal-water reaction and fission product decay. Models are included for considering fuel-rod swelling and rupture, energy transport across the fuel-to-cladding gap, and the thermal response of the canister. MOXY requires that time-dependent data during the blowdown process for the power normalized to the steady-state power, for the heat-transfer coefficient, and for the fluid temperature be provided as input. Internal models provide these parameters during the heatup and emergency cooling phases.IBM360;CDC7600; FORTRAN IV and Assembly language (IBM360), FORTRAN IV and COMPASS (CDC7600); OS/360 (IBM360) and SCOPE 2.1 (CDC7600); 300K bytes of storage (IBM360) or 110,000 (octal) words of small core memory (SCM) (CDC7600), standard input/output units, and 5 other units are required..
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- OSTI ID:
- 6460629
- Report Number(s):
- ANL/NESC-551; ON: DE83048551
- Country of Publication:
- United States
- Language:
- English
Similar Records
CONTEMPT-LT/028; CONTEMPT-LT/026; pressure-temperature response. [CDC7600,CYBER176; IBM360; FORTRAN IV and COMPASS (CDC7600), FORTRAN IV and BAL (IBM360)]
VIM1; VIM1X; Monte Carlo critical assembly analysis. [CDC7600; IBM360; FORTRAN IV (CDC7600), FORTRAN IV and BAL (IBM360)]
Related Subjects
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLOWDOWN
BWR TYPE REACTORS
COMPUTER CODES
ELECTROMAGNETIC RADIATION
ENERGY TRANSFER
FORTRAN
FUEL ELEMENTS
G CODES
HEAT TRANSFER
LOSS OF COOLANT
M CODES
MOLTEN METAL-WATER REACTIONS
PROGRAMMING LANGUAGES
R CODES
RADIATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
T CODES
THERMAL ANALYSIS
THERMAL RADIATION
V CODES
WATER COOLED REACTORS
WATER MODERATED REACTORS