Insights into neutron transport in a new multipurpose nuclear reactor
Luiz Paulo de Oliveira, Alexandre Pinho dos Santos Souza, Carlos Gabriel da Silva Santos, Iber\^e Souza Ribeiro J\'unior, Barbara Perez Gon\c{c}alves Silva, Marco Antonio Stanojev Pereira, Frederico Antonio Genezini

TL;DR
This study uses Monte Carlo simulations to analyze neutron transport and moderation in the Brazilian RMB reactor, revealing neutron spectrum distributions and effective moderation processes crucial for its multipurpose functions.
Contribution
It provides detailed neutron transport analysis in the RMB reactor using Monte Carlo methods, highlighting neutron spectrum shifts and moderation effectiveness in a new reactor design.
Findings
52% epithermal neutrons in core
100% thermal neutrons near reflector wall
Shift in neutron wavelength peak from 1.07 Å to 1.19 Å
Abstract
Neutron transport inside the reflector tank of the new Brazilian nuclear reactor, called the RMB (Brazilian Multipurpose Reactor), is investigated using the stochastic Monte Carlo method. One of the main characteristics of research nuclear reactors is the core power density, which is proportional to the neutron flux generated in the fission reaction. The RMB is part of the new generation of multipurpose reactors, and studying neutron transport is essential for the project to meet its objectives of producing radioisotopes, irradiating materials, and generating neutron beams for scientific investigations. The neutron moderation process in the reflector tank is very well described by Maxwellian distributions, which provide temperatures ranging from T = 331.5 K in the core to T = 266.8 K in the peripheral regions. The relative proportions reveal the predominance (52%) of epithermal neutrons…
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Taxonomy
TopicsNuclear reactor physics and engineering · Nuclear Physics and Applications · Radiation Therapy and Dosimetry
