酸化物燃料の照射挙動

抄録

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.