高速炉用金属燃料における被覆管内面侵食構造の解明
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概要
- 論文の詳細を見る
During steady-state irradiation of metallic fuel in fast reactors, rare-earth fission products can react with stainless steel cladding at the fuel-cladding interface. The authors conducted isothermal annealing tests with some diffusion couples to investigate the structure of the wastage layer formed at the interface. Candidate cladding alloys, ferritic-martensitic steel (PNC-FMS) and oxide-dispersion-strengthened (ODS) steel were assembled with rare-earth alloys, RE5 : La-Ce-Pr-Nd-Sm, which simulate the fission yield of rare-earth fission products. The diffusion couples were isothermally annealed in the temperature range of 500-650°C for up to 170 h. In both RE5/ODS-steel and RE5/PNC-FMS couples, the wastage layer of the two-phase region of the (Fe, Cr)17RE2 matrix phase with the precipitation of the (Fe, RE, Cr) phase was formed. The structure was similar to that formed in RE5/Fe-12Cr and RE5/HT9 couples, which implies that the reaction between REs and steel is not significantly influenced by the minor alloying elements within the candidate cladding materials. It was also clarified that the increase in the wastage layer thickness was diffusion-controlled. The temperature dependence of the reaction rate constants were formulated, which can be the basis for the quantification of the wastage layer growth.
著者
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Ogata Takanari
Central Res. Inst. Of Electric Power Ind.
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中村 勤也
Nuclear Research Laboratory, Central Research Institute of Electric Power Industry
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上羽 智之
Japan Atomic Energy Agency
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尾形 孝成
Nuclear Research Laboratory, Central Research Institute of Electric Power Industry
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稲垣 健太
Nuclear Research Laboratory, Central Research Institute of Electric Power Industry
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