LEU-HEU Mixed Core Conversion Thermal-hydraulic Analysis and Coolant System Upgrade Assessment for the MIT Research Reactor

The MIT Research Reactor (MITR) is in the process of converting from the current 93%-enriched U-235 highly-enriched uranium (HEU) fuel to the low enriched uranium (LEU, <20%-enriched U-235) fuel, as part of the global non-proliferation initiatives. A high-density, monolithic uraniummolybdenum (U-...

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Bibliografische gegevens
Hoofdauteur: Zhao, Yinjie
Andere auteurs: Hu, Lin-Wen
Formaat: Thesis
Gepubliceerd in: Massachusetts Institute of Technology 2023
Online toegang:https://hdl.handle.net/1721.1/147212