著者

「核燃料挙動」研究専門委員会

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.19, no.5, pp.303-323, 1977-05-30 (Released:2009-03-31)

参考文献数

87

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Irradiation behavior of oxide fuels for LWR and FBR was reviewed with emphasis on its chemical process and state. The following are described: progress and problems in research of irradiated oxide fuels for LWR and FBR; densification of fuel pellet; interaction between Zircaloy and fission products; corrosion of stainless steel; and effects of O/M ratio on properties of irradiated oxide fuel.