1. Fission gas release from UO2-dispersed graphite during irradiation
- Author
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Shunzo Omori, Muneo Handa, T. Fukuda, Yoshihisa Takahashi, Koreyuki Shiba, Shigeru Yamagishi, and Takaaki Tanifuji
- Subjects
Fission products ,Materials science ,Fission ,Annealing (metallurgy) ,Xenon-135 ,General Engineering ,Analytical chemistry ,chemistry.chemical_element ,Atmospheric temperature range ,Nuclear physics ,Xenon ,chemistry ,Graphite ,Irradiation - Abstract
In-pile release of 85mKr, 87Kr, 88Kr, 133Xe, 135Xe and 138Xe from natural graphite was measured over a temperature range of 100 to 950°C and that of 133I and 135I was estimated. The effects of fission rate and fission density on the fission gas release were examined. The β-decay process of iodine within and outside the graphite was observed to control the gross release of xenon. Possible mechanisms of an anomalous sink of 88Kr in the plot of log R B versus log λ were discussed. A new model for knock-out release was proposed on the basis of its temperature dependence found. These results were compared with those of post-irradiation experiments and explained by a mechanism whereby fission gas is trapped in defects created in graphite by fission and β-decay energy, and released through annealing of the defects.
- Published
- 1972
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