Neutron flux characterization of the beam port of the Missouri University of Science and Technology Reactor

Mubarak Albarqi, Raed Alsulami, Tayfun Akyurek, Joseph Graham*

*Corresponding author for this work

Research output: Contribution to journalArticlepeer-review

8 Citations (Scopus)

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) × 106 cm−2 s−1 and (7.3 ± 0.3) × 105 cm−2 s−1, respectively and were found to be in good qualitative agreement with the MCNP simulations.

Original languageEnglish
Pages (from-to)109-116
Number of pages8
JournalJournal of Radioanalytical and Nuclear Chemistry
Volume321
Issue number1
DOIs
Publication statusPublished - 15 Jul 2019
Externally publishedYes

Bibliographical note

Publisher Copyright:
© 2019, Akadémiai Kiadó, Budapest, Hungary.

Keywords

  • Beam port
  • Foil activation
  • MCNP
  • Monte Carlo
  • Neutron activation analysis
  • Neutron flux characterization

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