Affiliation:
1. Utah Nuclear Engineering Program, The University of Utah, Salt Lake City, Utah, USA
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.
Publisher
National Library of Serbia
Subject
Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering
Cited by
6 articles.
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