Albedo method applied for gamma radiation shielding

Authors

DOI:

https://doi.org/10.15392/2319-0612.2023.2250

Keywords:

Albedo, Nuclear Reactor, Radiation Shielding

Abstract

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.

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References

JACOBS, A. M. Experimental and theoretical considerations of the temperature coefficient for the Pennsylvania State University Research Reactor, Thesis for Master of Science, The Pennsylvania State University, USA, 1958

JACOBS, A. M. Two-Group Albedo theory and applications to temperature coefficient calculations, Nuclear Science and Engineering, v.6 p.147-151, 1959

CABRAL, R. G. et al. Two-Group Neutron Albedo theory: A different point of view to nuclear reactor analysis. In: IX ENCONTRO NACIONAL DE FÍSICA DE REATORES E TERMOHIDRAULICA, Caxambu, MG. Anais p.33-36, 1993

CABRAL, R. G. et al. application of two-group Neutron Albedo theory to neutronic calculation. In: V CONGRESSO DE ENERGIA NUCLEAR, Rio de Janeiro, RJ, 1994. Anais v.1, p.171-174, Associação Brasileira de Energia Nuclear, 1994.

CABRAL, R. G. et al. Noninterative calculation of effective Neutron multiplication factor by using two-group Neutron Albedo theory. In: X ENCONTRO NACIONAL DE FÍSICA DE REATORES E TERMOHIDRAULICA, Águas de Lindóia, SP. Anais v.1 p.31-34, 1995

CABRAL, R. G. et al. Neutronic Calculation for a fast assembly by using two-group Neutron Albedo theory. In: VI CONGRESSO GERAL DE ENERGIA NUCLEAR, Rio de Janeiro, RJ, 1996

CABRAL, R. G. et al. Neutronic calculations for multilayered Shields by using two-group Neutron Albedo theory. In: VI CONGRESSO GERAL DE ENERGIA NUCLEAR, Rio de Janeiro, RJ, 1996

AZEVEDO, S. S. de. Análise do método do Albedo aplicado a blindagem das radiações. Tese de mestrado em Engenharia Nuclear – Instituto Militar de Engenharia, 1998

DAMASO, V. C. Método multigrupo do Albedo aplicado a blindagens com múltiplas camadas. Tese de mestrado em Engenharia Nuclear – Instituto Militar de Engenharia, 1999.

DAMASO, V.C. et al. Método do Albedo a um grupo de energia aplicado a blindagem de radiação gama. Revista C&T, vol. XVII no. 2, 2o. quadrimestre de 2000.

ANISN-ORNL : A one dimension discrete ordinates transport code with anisotropic scattering. Oak Ridge Tenn., Radiation Schield Information Center, Oct. 1977. (CCC-254).

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Published

2023-07-11

How to Cite

Aguiar, A. E. de, Cabral, R. G., Oliveira, C. L. de, & Vellozo, S. de O. (2023). Albedo method applied for gamma radiation shielding. Brazilian Journal of Radiation Sciences, 11(3), 1–13. https://doi.org/10.15392/2319-0612.2023.2250

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