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Atoms 2016, 4(3), 20; doi:10.3390/atoms4030020

Neutrons and Gamma-Ray Dose Calculations in Subcritical Reactor Facility Using MCNP

Nuclear Engineering Department, King Abdulaziz University, P.O. Box: 80204, Jeddah 21589, Saudi Arabia
Academic Editor: Primoz Pelicon
Received: 10 April 2016 / Revised: 16 June 2016 / Accepted: 16 June 2016 / Published: 30 June 2016
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Abstract

In nuclear experimental, training and teaching laboratories such as a subcritical reactor facility, huge measures of external radiation doses could be caused by neutron and gamma radiation. It becomes imperative to place the health and safety of staff and students in the reactor facility under proper scrutiny. The protection of these individuals against ionization radiation is facilitated by expected dose mapping and shielding calculations. A three-dimensional (3D) Monte Carlo model was developed to calculate the dose rate from neutrons and gamma, using the ANSI/ANS-6.1.1 and the ICRP-74 flux-to-dose conversion factors. Estimation for the dose was conducted across 39 areas located throughout the reactor hall of the facility and its training platform. It was found that the range of the dose rate magnitude is between 7.50 E−01 μSv/h and 1.96 E−04 μSv/h in normal operation mode. During reactor start-up/shut-down mode, it was observed that a large area of the facility can experience exposure to a significant radiation field. This field ranges from 2.99 E+03 μSv/h to 3.12 E+01 μSv/h. There exists no noticeable disparity between results using the ICRP-74 or ANSI/ANS-6.1.1 flux-to-dose rate conversion factors. It was found that the dose rate due to gamma rays is higher than that of neutrons. View Full-Text
Keywords: radiation; neutron; gamma; flux; dose rate; reactor; MCNP radiation; neutron; gamma; flux; dose rate; reactor; MCNP
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This is an open access article distributed under the Creative Commons Attribution License which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited. (CC BY 4.0).

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MDPI and ACS Style

Xoubi, N. Neutrons and Gamma-Ray Dose Calculations in Subcritical Reactor Facility Using MCNP. Atoms 2016, 4, 20.

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