Thermal hydraulic analysis for the Oregon State TRIGA reactor using RELAP5-3D

Conference · Tue Jul 15 04:00:00 EDT 2008

OSTI ID:21113489

Marcum, W R; Woods, B G; Hartman, M ^[1]

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1. Nuclear Engineering Department, Oregon State University, OR 97330 (United States)

Thermal hydraulic analyses have being conducted at Oregon State University (OSU) in support of the conversion of the OSU TRIGA reactor (OSTR) core from high-enriched uranium (HEU) to low-enriched uranium (LEU) fuel as part of the Reduced Enrichment for Research and Test Reactors program. The goals of the thermal hydraulic analyses were to calculate natural circulation flow rates, coolant temperatures and fuel temperatures as a function of core power for both the HEU and LEU cores; calculate peak values of fuel temperature, cladding temperature, surface heat flux as well as departure from nuclear boiling ratio (DNBR) for steady state and pulse operation; and perform accident analyses for the accident scenarios identified in the OSTR safety analysis report. RELAP5-3D Version 2.4.2 was implemented to develop a model for the thermal hydraulic study. The OSTR core conversion is planned to take place in late 2008. (author)

• Research Organization: Argonne National Laboratory, Nuclear Engineering Division, RERTR Department, Argonne, IL (United States); Czech Technical University, Prague (Czech Republic)
• OSTI ID: 21113489
• Report Number(s): INIS-US--08N0001
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BOILING
COOLANTS
EDUCATIONAL FACILITIES
ENRICHMENT
FLOW RATE
HEAT FLUX
HIGHLY ENRICHED URANIUM
MODERATELY ENRICHED URANIUM
NATURAL CONVECTION
NUCLEAR FUELS
OSTR REACTOR
REACTOR ACCIDENTS
REACTOR OPERATION
SAFETY ANALYSIS
STEADY-STATE CONDITIONS
THERMAL HYDRAULICS