Upgrading the HFIR Thermal-Hydraulic Legacy Code Using COMSOL

Conference · Fri Oct 01 00:00:00 EDT 2010

OSTI ID:989720

Bodey, Isaac  ^[1]; Arimilli, Rao ^[1]; Freels, James D. ^[1]

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1. ORNL

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.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 989720
• Resource Relation: Conference: COMSOL Conference 2010 Boston - Boston, Massachusetts, United States of America - 10/7/2010 12:00:00 AM-10/9/2010 12:00:00 AM
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
DESIGN
ENRICHED URANIUM
HEAT TRANSFER
HFIR REACTOR
SAFETY ANALYSIS
Thermal-hydraulics
Nuclear Safety