Improved Shielding Design with an Accelerated Monte Carlo Simulation for a Neutron Generator at Missouri S&T
Abstract
Currently, Missouri University of Science and Technology (Missouri S&T) has a neutron generator that is limited in its operational time per year by regulatory limits. Previous work has identified key areas that require additional shielding and made recommendations; accordingly, this study was conducted to optimize the additional shielding design for the neutron generator at Missouri S&T to enable long-term usage. Dose analysis was performed using Monte Carlo simulation. Moreover, an automatic weight window generator - ADVANTG was employed to reduce the necessary computation time of the Monte Carlo simulation. The effectiveness of the proposed design is compared with previous work. Additional shielding offered significant dose reductions to 1.018, 1.127, 0.680, 1.243, and 1.400 mRem/h representing a decrease of 55.7%, 48.5%, 59.0%, 90.8%, and 70.5% for the north, south, west, east, and floor, respectively compared to similar values reported in previous studies. Additional shielding, from 5 cm to 20 cm in thickness, was suggested, depending on the current shielding. The neutron generator is projected to maintain a 300-hour operation time per year with the suggested shielding design.
Recommended Citation
H. Sahiner et al., "Improved Shielding Design with an Accelerated Monte Carlo Simulation for a Neutron Generator at Missouri S&T," Progress in Nuclear Energy, vol. 97, pp. 123 - 132, Elsevier, May 2017.
The definitive version is available at https://doi.org/10.1016/j.pnucene.2017.01.005
Department(s)
Nuclear Engineering and Radiation Science
Keywords and Phrases
Dosimetry; Intelligent systems; Neutron beams; Neutron sources; Neutrons; Shielding; Computation time; Current shielding; Neutron generators; Operation time; Regulatory limit; Science and Technology; Shielding design; Variance reductions; Monte Carlo methods; Monte Carlo simulation; Radiation dose
International Standard Serial Number (ISSN)
0149-1970
Document Type
Article - Journal
Document Version
Citation
File Type
text
Language(s)
English
Rights
© 2017 Elsevier, All rights reserved.
Publication Date
01 May 2017
Comments
This work is supported by the U.S. Nuclear Regulatory Commission Faculty Development Grant under Grant No. NRC-HQ-12-G-38-0039.