2023 Annual Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 504-3 Fuel Reprocessing

[2H06-07] Spent Fuel Management

Tue. Mar 14, 2023 11:25 AM - 12:00 PM Room H (13 Bildg.1F 1312)

Chair:Koichiro Takao(Tokyo Tech)

11:25 AM - 11:40 AM

[2H06] Management of plu-thermal spent fuel

(1)Study of the direct disposal concept

*Takumi Abe1, Kenji Nishihara1 (1. JAEA)

Keywords:plu-thermal, nuclear spent fuel, waste management, direct disposal, thermal analysis

Since the decay heat of plu-thermal spent fuel is large, it is expected that the disposal conditions for direct disposal such as the stationing interval will be more severe than those of UO2 spent fuel. In this study, heat conduction analysis around the waste body was performed using the finite element method to investigate the disposal conditions under which the maximum buffer material temperature is less than the limit value. As a result, several disposal concepts were obtained, such as extending the cooling period and increasing the area per waste body to about 13 times of that for UO2 fuel at a disposal depth of 1000 m.