Modeling the MIT Reactor Neutronics for LEU Conversion Studies

摘要

To investigate the possible use of high-density low enriched uranium (LEU)rnin the MIT Reactor, the core neutronic behavior has been modeled using thernMonte Carlo based codes MCNP for statics and MCODE for burnup. Thesernmodels have been validated using criticality, blade worth, and burnup reactivityrnmeasurement data from MITR-II Core #2. Preliminary studies indicate that thernLEU novel Mo-U fuel U7Mo can provide the reactivity needed to operate thernreactor for adequate life times. The LEU core design optimization to maximizernthe neutron flux is proceeding using these models.