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, page iv.
Mueller, Gary Edward, 1954-
Kumar, A. S. (Arvind S.)
Nuclear Engineering and Radiation Science
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 pages
© 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://merlin.lib.umsystem.edu/record=b6661726~S5
Dennis, Matthew L., "Feasibility study of plutonium based MOX fuel online burnup analysis using gamma spectroscopy" (2008). Masters Theses. 72.
Share My Thesis If you are the author of this work and would like to grant permission to make it openly accessible to all, please click the button above.