NT & RP Journal
EXPERIMENTAL AND MCNP5 BASED EVALUATION OF NEUTRON AND GAMMA FLUX IN THE IRRADIATION PORTS OF THE UNIVERSITY OF UTAH RESEARCH REACTOR
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Vol. XXVII, No. 3, Pp. 199-332
September 2012
UDC 621.039+614.876:504.06
ISSN 1451-3994

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Pages: 222-228

Authors:
Brooklyn Noble, Dong-Ok Choe, and Tatjana JevremoviŠ

Abstract


Neutron and gamma flux environment of various irradiation ports in the University of Utah training, research, isotope production, general atomics reactor were experimentally assessed and fully modeled using the MCNP5 code. The experimental measurements were based on the cadmium ratio in the irradiation ports of the reactor, flux profiling using nickel wire, and gamma dose measurements using thermo luminescence dosimeter. Full 3-D MCNP5 reactor model was developed to obtain the neutron flux distributions of the entire reactor core and to compare it with the measured flux focusing at the irradiation ports. Integration of all these analysis provided the updated comprehensive neutron-gamma flux maps of the existing irradiation facilities of the University of Utah TRIGA reactor.

Key words: neutron flux, TRIGA reactor, MCNP5 code, irradiation port, gamma dose

FULL PAPER IN PDF FORMAT (1.23 MB)

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