Neutron Flux Characterization of the Beam Port of the Missouri University of Science and Technology Reactor

Author

Mubarak Albarqi
Raed Alsulami
Tayfun Akyurek
Joseph T. Graham, Missouri University of Science and TechnologyFollow

Abstract

Neutron activation analysis was used to determine the thermal and epithermal neutron flux and its spatial distribution at the beam port of the Missouri University of Science and Technology Research Reactor. Gold foil irradiations were conducted and the determined flux was compared to Monte Carlo radiation transport predictions using the Monte Carlo N-particle code. The average experimental thermal (E < 0.55 eV) and epithermal (0.55 eV < E < 100 keV) fluxes were (5.7 ± 0.3) x 10⁶ cm^-2 s^-1 and (7.3 ± 0.3) x 10⁵ cm^-2 s^-1, respectively and were found to be in good qualitative agreement with the MCNP simulations.

Recommended Citation

M. Albarqi et al., "Neutron Flux Characterization of the Beam Port of the Missouri University of Science and Technology Reactor," Journal of Radioanalytical and Nuclear Chemistry, vol. 321, no. 1, pp. 109 - 116, Springer Netherlands, Jul 2019.

The definitive version is available at https://doi.org/10.1007/s10967-019-06561-2

Department(s)

Nuclear Engineering and Radiation Science

Keywords and Phrases

Beam Port; Foil Activation; MCNP; Monte Carlo; Neutron Activation Analysis; Neutron Flux Characterization

International Standard Serial Number (ISSN)

0236-5731; 1588-2780

Document Type

Article - Journal

Document Version

Citation

File Type

text

Language(s)

English

Rights

© 2019 Akadémiai Kiadó, All rights reserved.

Publication Date

01 Jul 2019