Title

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

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.

Department(s)

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)

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

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