GAM-HEAT: A computer code to compute heat transfer in complex enclosures. Revision 2

Technical Report · Tue Dec 01 00:00:00 EST 1992

DOI:https://doi.org/10.2172/10157530· OSTI ID:10157530

Cooper, R E; Taylor, J R

This report discusses the GAM{underscore}HEAT code which was developed for heat transfer analyses associated with postulated Double Ended Guilliotine 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 as discussed below, and also accounts for convective, conductive, and advective heat exchanges. The code is structured such that it is applicable for many situations involving heat exchange between surfaces within a radiatively passive medium.

• Research Organization: Savannah River Site (SRS), Aiken, SC (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 10157530
• Report Number(s): WSRC-TR-91-372-Rev.2; ON: DE93014724
• Resource Relation: Other Information: PBD: Dec 1992
• Country of Publication: United States
• Language: English

Related Subjects

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REACTOR SAFETY
RESEARCH
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MATERIALS TESTING REACTORS
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