Masters Theses


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.


Usman, Shoaib

Committee Member(s)

Mueller, Gary Edward, 1954-
Kumar, A. S. (Arvind S.)


Nuclear Engineering and Radiation Science

Degree Name

M.S. in Nuclear Engineering


Advanced Fuel Cycle Initiative (U.S.)


Missouri University of Science and Technology

Publication Date

Fall 2008

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.

Document Type

Thesis - Citation

File Type




Subject Headings

Gamma ray spectrometry
Mixed oxide fuels (Nuclear engineering)
Nondestructive testing
Plutonium as fuel

Thesis Number

T 9431

Print OCLC #


Link to Catalog Record

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