Neutron Flux Characterization of the Beam Port of the Missouri University of Science and Technology Reactor
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.
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
Mining and Nuclear Engineering
Keywords and Phrases
Beam Port; Foil Activation; MCNP; Monte Carlo; Neutron Activation Analysis; Neutron Flux Characterization
International Standard Serial Number (ISSN)
Article - Journal
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01 Jul 2019