Using Monte Carlo transport to accurately predict isotope production and activation analysis rates at the University of Missouri research reactor

• Published in: Journal of radioanalytical and nuclear chemistry Vol. 282; no. 1; pp. 255 - 259
• Main Authors: Peters, N. J., Brockman, J. D., Robertson, J. D.
• Format: Journal Article
• Language: English
• Published: Dordrecht Springer Netherlands 01-10-2009
• Subjects: Chemistry; Chemistry and Materials Science; Computer simulation; Diagnostic Radiology; Foils; Hadrons; Heavy Ions; Inorganic Chemistry; Isotopes; Mathematical models; Monitors; Monte Carlo methods; Nuclear Chemistry; Nuclear Physics; Nuclear research reactors; Physical Chemistry; Transport; Mo; Isotope production
• ISSN: 0236-5731; 1588-2780
• DOI: 10.1007/s10967-009-0163-y

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
99
Mo 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
99
Mo.