Computational Modeling of Neutron Shielding Using Deterministic Methods
In this paper, the so-called source-fixed problem (neutron shielding) in a non-multiplicative medium has been studied. Thus, neutron source shielding was computationally simulated using deterministic numerical methods to estimate the scalar and angular neutron fluxes in a one-dimensional domain. The...
| Autores: | , |
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| Tipo de recurso: | artículo |
| Estado: | Versión publicada |
| Fecha de publicación: | 2021 |
| País: | Brasil |
| Institución: | Universidade Federal do Rio Grande (FURG) |
| Repositorio: | Vetor (Online) |
| Idioma: | portugués |
| OAI Identifier: | oai:periodicos.furg.br:article/12877 |
| Acceso en línea: | https://periodicos.furg.br/vetor/article/view/12877 |
| Access Level: | acceso abierto |
| Palabra clave: | Blindagem de nêutrons Equação de transporte de nêutrons Modelagem Computacional Determinística Neutron shielding Neutron transport equation Deterministic Computational Modeling |
| Sumario: | In this paper, the so-called source-fixed problem (neutron shielding) in a non-multiplicative medium has been studied. Thus, neutron source shielding was computationally simulated using deterministic numerical methods to estimate the scalar and angular neutron fluxes in a one-dimensional domain. The linearized Boltzmann transport equation for neutral particles was employed in the modeling of the problems studied. In the numerical solution of the Boltzmann equation, certain approximations were considered and consolidated numerical methods were employed to generate accurate solutions. The Diamond Difference (DD), Step and Step Characteristic methods were used in the model problems addressed. The shielding configuration consisted of three materials, with the assembly sequence and material type varying as a function of the material-neutron interaction. Model problems were simulated and examined in order to identify efficient shielding for the emerging neutron flux. |
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