2018 Fall Meeting

Presentation information

Oral presentation

IV. Nuclear Plant Technologies » 401-1 Design and Manufacturing of Reactor Components and Transportation Vessel/Storage Facility

[3O08-12] Safety Enhancement and Assessment of LWR and Spent Fuel Transport Cask

Fri. Sep 7, 2018 2:45 PM - 4:05 PM Room O (D25 -D Building)

Chair:Susumu Naito(TOSHIBA)

3:15 PM - 3:30 PM

[3O10] Confirmation of heat removal performance of spent fuel storage and transport metal cask by heat transfer inspection

*Yuki Aramaki1, Jun Mizutani2, Takashi Kudo3, Takeshi Hiranuma1 (1. Hitachi-GE Nuclear Energy, Ltd., 2. Tokyo Electric Power Company Holdings, 3. Recyclable - Fuel Storage Company)

Keywords:metal cask, spent fuel dry storage, spent fuel transport, heat removal performance

This Report summarizes the results of heat transfer inspection of metal cask for spent fuel storage and transportation, which is conducted by Hitachi-GE Nuclear Energy, the manufacturer. To simulate the decay heat of the spent fuel in the metal cask an electric heater was used. The temperature of cask components measured by thermocouple, were then compared with the results of heat removal analysis. The temperatures are within the acceptance criteria, and therefore, it has confirmed that the heat removal performance of metal cask is satisfied.