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DOE OSTI · 2475032

Preliminary MITR Design-Demonstration Element Thermal-Hydraulics and Structural Analyses

Tano Retamales, Mauricio Eduardo·Yoon, SuJong
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Abstract

The United State High Performance Research Reactor (USHPRR) program aims to eliminate more than 200kg of High Enriched Uranium (HEU) from commerce annually by converting five U.S. high-performance research reactors and one associated critical assembly to Low Enriched Uranium (LEU) fuel using a high-density alloy of uranium-10 wt% molybdenum (U-10Mo). Massachusetts Institute of Technology Reactor (MITR) is one of five research reactors selected for this program. The objective of this report is to provide preliminary thermal-hydraulic and mechanical analyses of the hydrodynamic effects in the MITR Design Demonstration Element (DDE) under conservative approximations for the plate power distribution. This report provides details on the modeling approach and the simulation results obtained, including pressure, flow velocity, temperature, and oxide layer over the design demonstration experiment for the irradiation cycles in the Belgian Reactor (BR)-2.

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Tano Retamales, Mauricio Eduardo, Yoon, SuJong. 2022-10-02. Preliminary MITR Design-Demonstration Element Thermal-Hydraulics and Structural Analyses. https://www.osti.gov/biblio/2475032

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