Using Monte Carlo transport to accurately predict isotope production and activation analysis rates at the University of Missouri research reactor |
| |
Authors: | N J Peters J D Brockman J D Robertson |
| |
Institution: | (1) Department of Chemistry, University of Missouri, Columbia, MO 65211, USA;(2) University of Missouri Research Reactor, Columbia, MO 65211, USA |
| |
Abstract: | A detailed Monte Carlo N-Particle Transport Code (MCNP5) model of the University of Missouri research reactor (MURR) has been developed. The ability
of the model to accurately predict isotope production rates was verified by comparing measured and calculated neutron-capture
reaction rates for numerous isotopes. In addition to thermal (1/v) monitors, the benchmarking included a number of isotopes
whose (n, γ) reaction rates are very sensitive to the epithermal portion of the neutron spectrum. Using the most recent neutron
libraries (ENDF/B-VII.0), the model was able to accurately predict the measured reaction rates in all cases. The model was
then combined with ORIGEN 2.2, via MONTEBURNS 2.0, to calculate production of 99Mo from fission of low-enriched uranium foils. The model was used to investigate both annular and plate LEU foil targets in
a variety of arrangements in a graphite irradiation wedge to optimize the production of 99Mo. |
| |
Keywords: | |
本文献已被 SpringerLink 等数据库收录! |
|