1. ORIGEN2: A Versatile Computer Code for Calculating the Nuclide Compositions and Characteristics of Nuclear Materials;Croff;Nuclear Technol.,1983
2. GDE-588, “Thermal-Hydraulic Analysis Team (THAT) Guidebook,” Tech. Rep. GDE-588, Idaho National Laboratory (2020).
3. High-Density, Low-Enriched Uranium Fuel for Nuclear Research Reactors;Keiser;JOM,2003
4. Kim, S., Schnitzler, B., 2014. Advanced test reactor: Serpentine arrangement of highly enriched water-moderated uranium-aluminide fuel plates reflected by beryllium. In: International Handbook of Evaluated Criticality Safety Benchmarks, NEA/NSC/DOC (95)03/II, NEA-7231. Paris, France: OECD-NEA; HEU-THERM-022.
5. Irradiation Performance of U-Mo Monolithic Fuel;Meyer;Nucl. Energy Tech.,2014