Mathematical tools for calculating radiation shielding usually have difficult notations that could only be solved by computational methods. The Albedo’s method applied for calculation of shielding proves to be an excellent substitute in determining the incident beam fractions that are reflected, absorbed and transmitted, avoiding the use of the transport equation and diffusion approximation that are extremely important in nuclear reactor designs and irradiation calculations. Based on the simple following of the radiation current path, the method can be characterized as a graphical and analytical solution. This work explores the Albedo’s Method applied to 4-slab shielding with incidence of gamma radiation to an energy group compared to ANISN, computational method consecrated in the area of nuclear calculations.
The main objective of this research is to develop a three-group neutron Albedo algorithm
considering the up-scattering of neutrons in order to analyze the diffusion phenomenon in nonmultiplying
media. The neutron Albedo method is an analytical method that does not try to solve
explicit describing equations for the neutron fluxes [1,2]. Thus the neutron Albedo methodology is
very different from the conventional methodology, as the neutron diffusion theory model. Graphite
is analyzed as a model case. One major application is in the determination of the nonleakage
probabilities with more understandable results in physical terms than conventional radiation
transport method calculations.
Neste trabalho, o núcleo de um reator modular de pequeno porte (SMR) hipotético do tipo PWR, com um enriquecimento do combustível de 20% e potência de 50 MWe (150 MWt), foi simulado na condição de criticalidade. A 300 cm do vaso de pressão do SMR foi medida a dose efetiva de 1,33E+9 mSv, que mostrou a necessidade de calcular e instalar uma blindagem multilaminada no contexto do plano de proteção radiológica da instalação nuclear para fins de licenciamento e cumprimento das diretrizes pertinentes. Os dados disponíveis foram utilizados no dimensionamento do projeto básico do serviço de proteção radiológica da instalação, além da possibilidade de serem aplicados na elaboração do respectivo PSAR (Preliminary Safety Analysis Report).
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