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

Content Provider	Springer Nature Link
Author	Peters, N. J. Brockman, J. D. Robertson, J. D.
Copyright Year	2009
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 $^{99}$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.
Starting Page	255
Ending Page	259
Page Count	5
File Format	PDF
ISSN	02365731
Journal	Journal of Radioanalytical and Nuclear Chemistry
Volume Number	282
Issue Number	1
e-ISSN	15882780
Language	English
Publisher	Springer Netherlands
Publisher Date	2009-07-16
Publisher Place	Dordrecht
Access Restriction	One Nation One Subscription (ONOS)
Subject Keyword	$^{99}$Mo Isotope production Inorganic Chemistry Diagnostic Radiology Nuclear Physics, Heavy Ions, Hadrons Physical Chemistry Nuclear Chemistry
Content Type	Text
Resource Type	Article
Subject	Spectroscopy Pollution Health, Toxicology and Mutagenesis Radiology, Nuclear Medicine and Imaging Analytical Chemistry Public Health, Environmental and Occupational Health Nuclear Energy and Engineering

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