GAM-HEAT -- a computer code to compute heat transfer in complex enclosures. Revision 1
The GAM-HEAT code was developed for heat transfer analyses associated with postulated Double Ended Guillotine Break Loss Of Coolant Accidents (DEGB LOCA) resulting in a drained reactor vessel. In these analyses the gamma radiation resulting from fission product decay constitutes the primary source of energy as a function of time. This energy is deposited into the various reactor components and is re- radiated as thermal energy. The code accounts for all radiant heat exchanges within and leaving the reactor enclosure. The SRS reactors constitute complex radiant exchange enclosures since there are many assemblies of various types within the primary enclosure and most of the assemblies themselves constitute enclosures. GAM-HEAT accounts for this complexity by processing externally generated view factors and connectivity matrices, and also accounts for convective, conductive, and advective heat exchanges. The code is applicable for many situations involving heat exchange between surfaces within a radiatively passive medium. The GAM-HEAT code has been exercised extensively for computing transient temperatures in SRS reactors with specific charges and control components. Results from these computations have been used to establish the need for and to evaluate hardware modifications designed to mitigate results of postulated accident scenarios, and to assist in the specification of safe reactor operating power limits. The code utilizes temperature dependence on material properties. The efficiency of the code has been enhanced by the use of an iterative equation solver. Verification of the code to date consists of comparisons with parallel efforts at Los Alamos National Laboratory and with similar efforts at Westinghouse Science and Technology Center in Pittsburgh, PA, and benchmarked using problems with known analytical or iterated solutions. All comparisons and tests yield results that indicate the GAM-HEAT code performs as intended.
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 10179550
- Report Number(s):
- WSRC-TR-91-372-Rev.1; ON: DE93019280; TRN: 93:020017
- Resource Relation:
- Other Information: PBD: Feb 1991
- Country of Publication:
- United States
- Language:
- English
Similar Records
GAM-HEAT: A computer code to compute heat transfer in complex enclosures. Revision 2
Estimate of LOCA-FI plenum pressure uncertainty for a five-ring RELAP5 production reactor model
Related Subjects
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
HEAT TRANSFER
COMPUTER CALCULATIONS
SPECIAL PRODUCTION REACTORS
LOSS OF COOLANT
G CODES
REACTOR SAFETY
SAVANNAH RIVER PLANT
TRANSIENTS
TEMPERATURE GRADIENTS
220900
220600
990200
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
MATHEMATICS AND COMPUTERS