Title

Review and Characterization of Best Candidate Isotopes for Burnup Analysis and Monitoring of Irradiated Fuel

Abstract

This research is an extension of feasibility study of MOX fuel online burnup analysis. A multitude of fission products identified as candidates have been scrutinized for their suitability of burnup analysis and spent fuel analysis. Best isotopes obtained for analysis by investigating half-life, fission yield, branching ratios, production modes, thermal neutron absorption cross section and fuel matrix diffusivity. ¹³²I and ⁹⁷Nb are identified as good isotope candidates for on-line burnup analysis. ¹³²I is also a good candidate for plutonium/uranium discrimination due to the large difference in the fission yield of the isotope. For interim storage monitoring the well-established cesium isotopes appears to be the best choices unless the data gaps are addressed. Other alternate for cesium for interim monitoring is ¹³¹I, ¹⁴⁰La, and ⁹⁵Nb at the present time. Selection of one over the other choice must be made based on application. For the long-term storage monitoring ⁹⁴Nb is the only attractive candidate. It has a low diffusion rate of ~10ˉ¹¹ cm²/s, an almost zero neutron absorption cross section making it burnup history independent and decent gamma yield of 1.44E-09. In addition, the paper also identifies the data gaps for developing a robust burnup analysis tool using gamma spectroscopy. © 2014 Elsevier Ltd. All rights reserved.

Department(s)

Mining and Nuclear Engineering

Keywords and Phrases

Burnup Credit; Gamma Spectroscopy; Half Lives; Nuclear Fuel

Document Type

Article - Journal

Document Version

Citation

File Type

text

Language(s)

English

Rights

© 2014 Elsevier, All rights reserved.


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