MCNP and CFD Modeling for Potential High-Power Configuration of Missouri S&T Reactor

Utilization of nuclear research reactors is high importance for education and training, development, many other applications. However, less effective utilization encountered in mainly due to limitations power levels related experimental facilities. Such limitations, however, have led different global owners consider upgrading the their accommodate increase demands. To without replacing major components, a pair essential analyses must be performed, namely neutronic evaluation fission thermal-hydraulic heat removal from reactor core. In this work, conceptual upgrade core design configuration MSTR, or Missouri University Science Technology Reactor (200 kilowatts (kW)), demonstrated. The MSTR high-power (MSTR-HPC) aims achieve neutron flux demonstrate level with greater flexibility adaptability while not exceeding safety limits. MSTR-HPC involves uprating 2 megawatts (MW), reconfiguring core, changing fuel meat type, inclusion trap (FT) facility, others. addition, includes three in-core irradiation facilities, FT, bare rabbit tube (BRT), cadmium (CRT). was carried out using Monte Carlo N-particle Code (MCNP), version 6. behavior MSTR-HPCs’ hot-channel has been assessed by means ANSYS Fluent evaluate satisfaction requirements design. results obtained shown that demonstrated maximum higher than current two orders magnitude. composite BeO/graphite reflector blocks able sustain critically operate continuously at full 61 days. regards hottest plate MSTR-HPC, determined temperature regions below operation mass flow rate 39.86 kg/s (10.644 gallon/s) sufficient removing generated heat. conclusion, its enhancement capabilities maintaining limits, which are enhancing larger window time.