4.4 Article

Computational analysis of the dose rates at JSI TRIGA reactor irradiation facilities

Journal

APPLIED RADIATION AND ISOTOPES
Volume 130, Issue -, Pages 140-152

Publisher

PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.apradiso.2017.09.022

Keywords

Research reactor; TRIGA; Irradiation positions; Neutron flux and spectrum; gamma flux and spectrum; Flux to dose conversion factors; ICRP-74; ICRP-21; ANSI-ANS6.1.11977

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The JSI TRIGA Mark II, IJS research reactor is equipped with numerous irradiation positions, where samples can be irradiated by neutrons and gamma-rays. Irradiation position selection is based on its properties, such as physical size and accessibility, as well as neutron and gamma-ray spectra, flux and dose intensities. This paper presents an overview on the neutron and gamma-ray fluxes, spectra and dose intensities calculations using Monte Carlo MCNP software and ENDF/B-VII.0 nuclear data libraries. The dose-rates are presented in terms of ambient dose equivalents, air kerma, and silicon dose equivalent. At full reactor power the neutron ambient dose equivalent ranges from 5.5 x 10(3)Sv h(-1) to 6 x 10(6)Svh(-1), silicon dose equivalent from 6 x 10(2)Gy/h(si) to 3 x 10(5)Gy/h(si), and neutron air kerma from 4.3 x 10(3)Gy h(-1) to 2 x 10(5)Gy h(-1) Ratio of fast (1 MeV < E) vs. thermal neutrons (E < 0.625 eV) ranges from 1.5 to 8.4 x 10(-2), gamma ray ambient dose equivalent at full reactor power from 3.4 x 10(3)Sy h(-1) to 3.6 x 10(5)Sv h(-1) and gamma air kerma range 3.1 x 10(3)Gy h(-1) to 2.9 x 10(5)Gy h(-1).

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