Obtenção dos fluxos de neutrôns total e térmico na mesa giratória do reator TRIGA MARK I IPR-R1 utilizando o método Monte Carlo

• Ano de defesa: 2011
• Autor(a) principal: Bruno Teixeira Guerra
• Tipo de documento: Dissertação
• Tipo de acesso: Acesso aberto
• Idioma: por
• Instituição de defesa: Universidade Federal de Minas Gerais; UFMG
• Palavras-chave em Português: Nêutrons; Reator triga; IPR-R1; Engenharia nuclear
• Link de acesso: http://hdl.handle.net/1843/MBAM-8LAN87

The IPR-R1 is a reactor type TRIGA, Mark-I model, manufactured by the General Atomic Company and installed at Nuclear Technology Development Centre (CDTN) of Brazilian Nuclear Energy Commission (CNEN), in Belo Horizonte, Brazil. It is a light water moderated and cooled, graphite-reflected, open-pool type research reactor. IPR-R1 works at 100 kW but it will be briefly licensed to operate at 250 kW. It presents low power, low pressure, for application in research, training and radioisotopes production. The fuel is an alloy of zirconium hydride and uranium enriched at 20% in 235U. The goal this work is modelling of the IPR-R1 Research Reactor Triga using the codes MCNPX2.6.0 (Monte Carlo N-Particle Transport eXtend) and MCNP5 to the calculating the neutron flux in the carousel facility. In each simulation the sample was placed in a different position, totaling forty positions around of the reactor core. The comparison between the results obtained with experimental values from other work showing a relatively good agreement. Moreover, this methodology is a theoretical tool in validating of the experimental values and necessary for determining neutron flux which can not be accessible experimentally.