Computational Analysis of Gamma-Ray and Fast Neutron Attenuation performance of some Thorium and Uranium Compounds

Ahmed Osman

doi:10.15392/2319-0612.2025.2868

Autores

Ahmed Osman Jouf University https://orcid.org/0000-0001-5351-0440 (não autenticado)

DOI:

https://doi.org/10.15392/2319-0612.2025.2868

Palavras-chave:

Eficácia da blindagem, Absorção de energia, Número atómico efetivo, Secção transversal de remoção efectiva

Resumo

A avaliação da eficácia da proteção contra a radiação de alguns compostos, incluindo Fe, Th, Y, Nb, Ta, Ti e U, foi calculada para a absorção de energia e interação total na gama de energia dos fotões de 0,015 a 15 MeV. O número atómico efetivo (Z_eff) destes compostos foi determinado através dos coeficientes de atenuação de massa (µ/ρ, cm²/g) e de absorção de energia de massa (µ/ρ, cm²/g). Por conseguinte, os valores de Z_eff foram calculados para a interação total dos fotões (Z_Ieff) e a absorção de energia (Z_Aeff) utilizando os códigos Py-MLBUF e Phy-X/PSD. Além disso, a secção transversal de remoção efectiva para neutrões rápidos (ΣR, cm^-1) e os comprimentos de atenuação foram calculados para investigar as caraterísticas de atenuação de neutrões rápidos. Os resultados apresentados mostraram que, Z_eff de S1 (UO₂) e S2 (ThSiO₄) são comparativamente mais elevados do que os Z_eff dos restantes compostos, enquanto S7 (Fe(UO₂)₂(PO₄)_2.8(H₂O)) possui os valores mais baixos de Z_eff. Os resultados obtidos também mostram que Z_Aeff deve ser usado em vez de Z_Ieff quando a quantidade em questão é a dissipação de energia. Além disso, os valores calculados de Σ_R para os compostos testados foram encontrados próximos e variaram de 0,079 cm^-1 para S4 a 0,146 cm^-1 para S1. Além disso, a comparação dos valores calculados para diferentes parâmetros de proteção revelou uma boa concordância entre os métodos propostos. Por último, este estudo poderá ser útil para aplicações destes compostos em requisitos de proteção contra raios gama e neutrões rápidos em diferentes domínios, tais como os ciclos do combustível nuclear e a proteção médica em ambientes de manuseamento de urânio.

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Biografia do Autor

Ahmed Osman, Jouf University

Assistant professor of nuclear physics, Physics Department, College of Science, Jouf University, P.O. Box 2014, Sakaka 72388, Saudi Arabia

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