Feasibility Study of MOX Fuel Online Burn Up Analysis


This research is an extension of well established Non-Destructive Analysis of UO2 fuel using gamma spectroscopy of Cs-137 and other related isotopes. Given the performance similarities between UO2 fuel and MOX fuel, investigations are underway to develop similar correlation for MOX. MOX fuel burnup and decay simulations are being performed using ORIGEN-ARP (Oak Ridge Isotope Generation and Depletion Code - Automatic Rapid Processing). Simulation results are being analyzed and will be used to determine performance specifications of a detection system for field applications. Analysis of isotopic activity from irradiated fuel will be used to develop correlations to determine burn-up and Plutonium content of MOX fuel. These results will be particularly useful in view of the recent interest in MOX fuel.


Nuclear Engineering and Radiation Science

Keywords and Phrases

Computer Simulation; Decay Simulations; Gamma Rays; Gamma Spectroscopy; Isotopic Activity; Nondestructive Examination; Nuclear Fuels; Plutonium; Uranium Dioxide

Document Type

Article - Conference proceedings

Document Version


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© 2006 American Nuclear Society (ANS), All rights reserved.

Publication Date

01 Jan 2006

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