Investigation of gamma radiation shielding features for modified structural materials for nuclear energy and nuclear medicine
In this paper, shielding characteristics of three concrete samples with different B4C,Fe3O4,and BaSO4 contents were examined by determining their theoretical and experimental mass attenuation coefficients at photon energies of 15 MeV. The mass attenuation coefficients ?m were theoretically calculate...
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Published in: | Nuclear technology & radiation protection Vol. 38; no. 2; pp. 108 - 115 |
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Main Authors: | , , , , |
Format: | Journal Article |
Language: | English |
Published: |
Belgrade
Vinca Institute of Nuclear Sciences
01-01-2023
VINCA Institute of Nuclear Sciences |
Subjects: | |
Online Access: | Get full text |
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Summary: | In this paper, shielding characteristics of three concrete samples with
different B4C,Fe3O4,and BaSO4 contents were examined by
determining their theoretical and experimental mass attenuation coefficients
at photon energies of 15 MeV. The mass attenuation coefficients ?m were
theoretically calculated using the chemical compositions of samples with the
XCOM program. Then the linear attenuation coefficients ? were calculated
by knowing the ?m values. Elekta Axesse accelerator was used to experimentally
determine the linear attenuation coefficient ? of samples with various
impurities. The ? value of 0.4699 cm-1, 0.6072 cm-1, and 0.7194mcm-1 was
obtained for the blank sample, sample with magnetite, and sample with barite, respectively, at 15 MeV. The results were compared with coefficients
obtained by XCOM and indicated a good agreement between the two methods. The
linear attenuation coefficient was evaluated to calculate the half- and
tenth-value layers. Compared to conventional concrete, the linear
attenuation coefficient for concrete with the highest barite content
increased by 53.1 %, and the thickness of the half-attenuation layer
decreased by 34.7 %. Such a sample can be used as a building material for
medical centers and nuclear power plants. |
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ISSN: | 1451-3994 1452-8185 |
DOI: | 10.2298/NTRP2302108Z |