Neutronic Analyses for HEU to LEU fuel conversion of the Massachusetts Institute of Technology.

Wilson, E. H. ; Newton, T. H. ; Bergeron, A. ; Horelik, N. ; Stevens, J. G (Nuclear Engineering Division) ; ( NS)

关键词: ENRICHED URANIUM;    HIGHLY ENRICHED URANIUM;    IRRADIATION;    MIXTURES;    MOLYBDENUM;    NEUTRON BEAMS;    NEUTRON FLUX;    NUCLEAR WEAPONS;    PERFORMANCE;    POWER REACTORS;    PROLIFERATION;    RESEARCH AND TEST REACTORS;    RESEARCH REACTORS;    SAFETY;    URANIUM;   

DOI  :  10.2172/1008288
RP-ID  :  ANL/RERTR/TM-10-40
PID  :  OSTI ID: 1008288
Others  :  TRN: US1101625

美国|英语

来源: SciTech Connect

【 摘 要 】

The Massachusetts Institute of Technology (MIT) reactor (MITR-II), based in Cambridge, Massachusetts, is a research reactor designed primarily for experiments using neutron beam and in-core irradiation facilities. It delivers a neutron flux comparable to current LWR power reactors in a compact 6 MW core using Highly Enriched Uranium (HEU) fuel. In the framework of its non-proliferation policies, the international community presently aims to minimize the amount of nuclear material available that could be used for nuclear weapons. In this geopolitical context, most research and test reactors both domestic and international have started a program of conversion to the use of Low Enriched Uranium (LEU) fuel. A new type of LEU fuel based on a mixture of uranium and molybdenum (UMo) is expected to allow the conversion of compact high performance reactors like the MITR-II. This report presents the results of steady state neutronic safety analyses for conversion of MITR-II from the use of HEU fuel to the use of U-Mo LEU fuel. The objective of this work was to demonstrate that the safety analyses meet current requirements for an LEU core replacement of MITR-II.