主催: The Japan Society of Mechanical Engineers
会議名: 第30回 原子力工学国際会議（ICONE30）
開催日: 2023/05/21 - 2023/05/26
The study of reactor fuel degradation behaviors under severe accidents have great significance for the safety of nuclear power plants and the formulation of management measures. Annular fuel is one kind of new-type fuel, which is composed of inner/outer cladding, inner/outer coolant channel and middle annual fuel pellet. Annular fuel has become one of the main development objects in many countries because of its economy and safety. At present, the research on the degradation behaviors of annular fuel under severe accident is still insufficient. Based on this reason, an out-of-pile visualization high temperature experimental system is built. The degradation experiment of annular fuel simulation rod is carried out based on the alternative cladding material-Al and the real cladding material-Zr. The temperature variation and visualization process data of the simulation rod are obtained. The degradation behaviors of annular fuel are further analyzed based on the experimental results.
