Feasibility study of plutonium based MOX fuel online burnup analysis using gamma spectroscopy
"The research presented here is based on the well defined Non-Destructive Analysis (NDA) of UO₂ fuel using gamma spectroscopy of ¹³⁷Cs and other related isotopes; however, limited investigation has occurred using these NDA techniques for plutonium based mixed-oxide (MOX) fuel. Therefore, since no MOX fuel assemblies were available for this research, simulations were performed using the computer code ORIGEN-ARP to first determine fission products that could serve as a signature for a burnup correlation. Further investigation determined that ¹³⁷Cs and ¹⁰⁶Ru-¹⁰⁶Rh were suitable MOX NDA fission products"--Abstract, leaf iv.
Mueller, Gary Edward, 1954-
Kumar, A. S. (Arvind S.)
Mining and Nuclear Engineering
M.S. in Nuclear Engineering
Advanced Fuel Cycle Initiative (U.S.)
Missouri University of Science and Technology
Journal article titles appearing in thesis/dissertation
- MOX fuel burnup analysis using non-destructive gamma spectroscopy - part 1, ORIGEN simulation and candidate peaks identification
- MOX fuel burnup analysis using non-destructive gamma spectroscopy - part 2, feasibility of ¹⁰⁶Ru peak
x, 55 leaves
© 2008 Matthew L. Dennis, All rights reserved.
Thesis - Citation
Gamma ray spectrometry
Mixed oxide fuels (Nuclear engineering)
Plutonium as fuel
Print OCLC #
Link to Catalog Record
Full-text not available: Request this publication directly from Missouri S&T Library or contact your local library.http://laurel.lso.missouri.edu/record=b6661726~S5
Dennis, Matthew L., "Feasibility study of plutonium based MOX fuel online burnup analysis using gamma spectroscopy" (2008). Masters Theses. 72.
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