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DOE OSTI · 989720

Upgrading the HFIR Thermal-Hydraulic Legacy Code Using COMSOL

Bodey, Isaac·Arimilli, Rao·Freels, James D.
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Abstract

Modernization of the High Flux Isotope Reactor (HFIR) thermal-hydraulic (TH) design and safety analysis capability is an important step in preparation for the conversion of the HFIR core from a high enriched uranium (HEU) fuel to a low enriched uranium (LEU) fuel. Currently, an important part of the HFIR TH analysis is based on the legacy Steady State Heat Transfer Code (SSHTC), which adds much conservatism to the safety analysis. The multi-dimensional multi-physics capabilities of the COMSOL environment allow the analyst to relax the number and magnitude of conservatisms, imposed by the SSHTC, to present a more physical model of the TH aspect of the HFIR.

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22 GENERAL STUDIES OF NUCLEAR REACTORSDESIGNENRICHED URANIUMHEAT TRANSFERHFIR REACTORNuclear SafetySAFETY ANALYSISThermal-hydraulics

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Bodey, Isaac, Arimilli, Rao, Freels, James D.. 2010-10-01. Upgrading the HFIR Thermal-Hydraulic Legacy Code Using COMSOL. https://www.osti.gov/biblio/989720

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