PRELIMINARY CALCULATION OF THE CORE OF THE RMB-BRAZILIAN MULTIPURPOSE REACTOR

Autores

  • Rubens Souza dos Santos Instituto de Engenharia Nuclear

Resumo

 

The paper shows some results of neutronic calculation of the Project of RMB - Multipurpose Brazilian Reactor with thermal power of 30MW [1]. In that reactor, a project of the CNEN/Brazil, under the leadership of the IPEN/ São Paulo, is calculated the reactor multiplication effective factor and the fast and thermal neutron flux, in the steady state regime. It has utilized a computer program based on multigroup diffusion theory; in our case we have used two energy groups, Two-Dimensional X-Y in the space

Biografia do Autor

Rubens Souza dos Santos, Instituto de Engenharia Nuclear

Education: Doctor in Science in Nuclear Engineering (D.Sc.) – Federal University of Rio de Janeiro – Brazil, 2004. Master in Science in Nuclear Engineering (M.Sc.) – Military Institute of Engineering – Brazil, 1981. Degree in Physics (B.Sc.) - Federal University of Rio de Janeiro – Brazil, 1978. Research Interests: Reactor Physics, Accelerator Driven Systems, Reactor Safety, Numerical Calculations. Present Positions: Researcher in the Reactor Division from Nuclear Engineering Institute IEN/CNEN, also Professor in the Master Course of the Nuclear Engineering Institute. Researcher proponent of National Institutes of Science and Technology (INCT) of Innovative Reactors.

Referências

CNEN/DPD/RMB, “Cálculo iterativos neutrônica/termo-hidráulica para determinar a potência do reator no início de vida”, RMB-10100-RD-007, 2010.

Rubens S Santos, “Dynamics of Nuclear Reactor Cores based on One and Two-Dimensional Multigroup Diffusion Theory”, X ENFIR, 1995.

Capa Progress Report 2013-2014

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Publicado

2015-12-04

Como Citar

Santos, R. S. dos. (2015). PRELIMINARY CALCULATION OF THE CORE OF THE RMB-BRAZILIAN MULTIPURPOSE REACTOR. Instituto De Engenharia Nuclear: Progress Report, (2), 61. Recuperado de https://revistas.ien.gov.br/index.php/ienprogressreport/article/view/218

Edição

n. 2 (2015): IEN - Progress Report 2013-2014 n.2

Seção

Engineering and Reactor Safety