Abstracts and Available Papers Presented at the Meeting
Thermal Hydraulic Analysis for the Oregon State TRIGA Reactor Using RELAP5-3D
W. R. Marcum, B. G.
Woods, M. Hartman
Nuclear Engineering Department
Oregon State University, OR USA 9733
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.
Full paper in PDF format
Hydraulic Analysis for the Oregon State TRIGA Reactor
Using RELAP5-3D, W.R. Marcum et al.
[PDF, 413KB, 10 pages]
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Dr. Jordi Roglans-Ribas
Technical Director, RERTR Department
Nuclear Engineering Division – 362
Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439
Fax: +1 630-252-5161