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Fission gas behavior in mixed-oxide fuel during transient overpower. [LMFBR]

E.H. Randklev, H.A. Treibs, Bernard Mastel, D.L. Baldwin

Abstract

Fission gas behavior can be important in determining fuel pin and core performance during a reactor transient. The results are presented of examinations characterizing the changes in microstructural distribution and retention of fission gas in fuel for a series of transient overpower (50 cents/s) tested mixed-oxide fuel pins and their steady state siblings.

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Key concepts: Transient (computer programming), Nuclear engineering, MOX fuel, Fission, Materials science, Fuel element failure, Environmental science, Nuclear reactor core