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.
S. Usman and M. L. Dennis, "Feasibility Study of MOX Fuel Online Burn Up Analysis," Proceedings of the 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06, American Nuclear Society (ANS), Jan 2006.
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
Article - Conference proceedings
© 2006 American Nuclear Society (ANS), All rights reserved.
01 Jan 2006