Experimental and MCNP5 based evaluation of neutron and gamma flux in the irradiation ports of the University of Utah research reactor
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 irra...
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| Principais autores: | , , |
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| Format: | Artigo |
| Sprog: | Inglês |
| Udgivet: |
VINCA Institute of Nuclear Sciences
2012-01-01
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| Serier: | Nuclear Technology and Radiation Protection |
| Fag: | |
| Online adgang: | http://www.doiserbia.nb.rs/img/doi/1451-3994/2012/1451-39941203222N.pdf |
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