Americium-beryllium shield container optimization with new high alloyed stainless steel and composite material using MCNPX code
In this paper the goal is to optimize a shield for the americium-beryllium radioactive source, which generates a mixed neutron and gamma-ray radiation field, using two different materials designed with simultaneous moderation and absorption of neutrons and gamma-ray shielding in mind: a new...
| Main Authors: | , , |
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| Format: | Article |
| Language: | English |
| Published: |
VINCA Institute of Nuclear Sciences
2023-01-01
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| Series: | Nuclear Technology and Radiation Protection |
| Subjects: | |
| Online Access: | https://doiserbia.nb.rs/img/doi/1451-3994/2023/1451-39942302096H.pdf |
| Summary: | In this paper the goal is to optimize a shield for the americium-beryllium
radioactive source, which generates a mixed neutron and gamma-ray radiation
field, using two different materials designed with simultaneous moderation
and absorption of neutrons and gamma-ray shielding in mind: a new type of
stainless steel and epoxy resin (C21H25ClO5) composite with a 40% NiO
additive. For this purpose, MCNPX was used and the equivalent dose rate for
both types of radiation was calculated. After the optimization process, the
shield volume experienced a 54% reduction while its weight, due to the use of
a steel alloy, was increased by 3.56 %. At a distance of 1 m from the center
of the source, the equivalent dose rate was reduced by 10.98% in comparison
to that of the original system. |
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| ISSN: | 1451-3994 1452-8185 |