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ICRP, conversion coefficients for use in radiological protection against external radiation. ICRP publication74., Annals of the ICRP, Volume 26 No. 3/4 (1996).

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Article

Analysis of the Impact of Cross-sectional Data Discrepancies on the Effectiveness of Radiation Shielding Design Using Monte Carlo Codes

1Department of physical sciences Karatina University, P.O Box 1957-10101, Karatina Kenya


International Journal of Physics. 2019, Vol. 7 No. 2, 63-65
DOI: 10.12691/ijp-7-2-5
Copyright © 2019 Science and Education Publishing

Cite this paper:
Jeremiah Monari Kebwaro. Analysis of the Impact of Cross-sectional Data Discrepancies on the Effectiveness of Radiation Shielding Design Using Monte Carlo Codes. International Journal of Physics. 2019; 7(2):63-65. doi: 10.12691/ijp-7-2-5.

Correspondence to: Jeremiah  Monari Kebwaro, Department of physical sciences Karatina University, P.O Box 1957-10101, Karatina Kenya. Email: jeremiahkebwaro@gmail.com

Abstract

The effect of cross-sectional data discrepancies on the effectiveness of radiation shielding design has been investigated in this paper. The MCNP code with cross-sections from ENDF/B-V and ENDF/B-VII has been used to determine the gamma ray dose equivalent, H*(10), behind a lead glass shield enclosing a slow neutron source. It is observed that the radiative capture gamma ray dose behind the shield is higher when ENDF/B-V cross-sections are used compared to that produced by ENDF/B-VII cross-sections. The discrepancy is due to absence of energetic primary gamma rays when ENDF/B-VII is used. The results show that shielding design using ENDF/B-VII cross-sections could underestimate the shield by a fair margin and compromise safety. It is therefore necessary to consider more than one release of ENDF/B when using lead glass for shielding slow neutron capture gamma rays. The discrepancies need to be addressed in the next releases.

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