Estimate of Radiation Release from MIT Reactor with Un-finned LEU Core during Maximum Hypothetical Accident

Published: May 01, 2017


Kaichao Sun, Lin-wen Hu, Thomas Henderson Newton, Erik Wilson, Arne Olson


The Massachusetts Institute of Technology Reactor (MITR-II) is a research reactor in Cambridge, Massachusetts designed primarily for experiments using neutron beam and in-core irradiation facilities. At 6 MW, it delivers neutron flux and energy spectrum comparable to LWR power reactors in a compact core using highly enriched uranium (HEU) fuel. In the framework of non-proliferation policy, the international community aims to minimize the use of HEU in civilian facilities. Within this context, research and test reactors have started a program to convert HEU fuel to low enriched uranium (LEU) fuel. A new type of LEU fuel based on a high density allow of uranium and molybdenum (U-10MO) is expected to allow the conversion of U.S. domestic high performance reactors like MITR. The current study focuses on the impacts of MITR Maximum Hypothetical Accident (MHA), which is also the Design Basis Accident (DBA), with LEU fuel. The MHA for the MITR is postulated to be a coolant flow blockage in the fuel element
Citation: Progress in Nuclear Energy
Volume: 92
Pub Type: Journals

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LEU COnversion, Accident analysis, radiation release
Created May 01, 2017, Updated March 06, 2017