Article ID Journal Published Year Pages File Type
7968155 Journal of Nuclear Materials 2014 12 Pages PDF
Abstract
We thank R. Konings et al. for their interest and their valuable critical discussion of our article regarding the fission product release from irradiated oxide fuel during thermal treatment and reply to their comments appearing in this issue. Their feedback stimulated us to give more details on the sampling procedure of investigated materials as well as the measurement procedure in order to exclude misunderstandings. The release curves for iodine and cesium are compared to blank profiles and reanalyzed to demonstrate the features of inductive heating approach applied in authors' recent study on FP release under inert and oxidizing conditions.
Related Topics
Physical Sciences and Engineering Energy Nuclear Energy and Engineering
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