MCNP5 modeling of the IPR-R1 TRIGA reactor for criticality calculation and reactivity determination - da Silva, Clarysson A.M.; Pereira, Claubia; Guerra, Bruno T.; Veloso, Maria Auxiliadora F.; Costa, Antonella L.; Dalle, Hugo M.; Menezes, Maria Ângela de B.C. (Nuclear engineering and design, 2011)
Keywords: Applied sciences; Controled nuclear fusion plants; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; Fuels; Insertion; Installations for energy generation and conversion: thermal and electrical energy; Mathematical models; Neutron flux; Nuclear engineering; Nuclear fuels; Nuclear power generation; Nuclear power plants; Nuclear reactor components; Nuclear reactors; Evaluation; Neutron flux; Neutron activation analysis; Radioisotope; Modeling; Standards; Nuclear reactor; Nuclear energy; Nuclear power plant; Reactor material; Relative error; Research reactor; Criticality