XMA analysis of undissolved materials observed in NSRR short irradiated uranium dioxide fuel.

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概要

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• After a short irradiation of UO<SUB>2</SUB> fuels with and without SiO<SUB>2</SUB>+ AI<SUB>2</SUB>O<SUB>3</SUB> additive in NSRR, a comparative study of the fission products (FP) dissolved in nitric acid and undissolved materials was performed. Results of the study were : (1) The additive fuel behaved similarly to non-additive fuel. (2) In both types of fuels, the undissolved materials in dried out solution were not FP but metals existing from the fuel fabrication stage. (3) The NSRR short irradiation had great influence on the shape of the undissolved components without changing the as-fabricated compositions.

• 一般社団法人 日本原子力学会の論文

著者

• KANAZAWA Hiroyuki

  Nuclear Safety Research Center, Japan Atomic Energy Research Institute

• SASAJIMA Hideo

  Nuclear Safety Research Center, Japan Atomic Energy Research Institute

• YANAGISAWA Kazuaki

  Nuclear Safety Research Center, Japan Atomic Energy Research Institute

関連論文

• XMA analysis of undissolved materials observed in NSRR short irradiated uranium dioxide fuel.

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