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)

3:30 PM - 3:45 PM

[3O11] Study on Heat Flow Analysis Modeling for Transport Packages with Radiation Fins

*Tatsuya Ito1, Hironori Mizobuchi1, Shigeo Honda1, Haruaki Kikuchi1, Tatsuya Minami2 (1. OCL CORPORATION, 2. Nuclear Fuel Transport Co., Ltd.)

Keywords:CASK, HEAT FLOW ANALYSIS, FIN, NATURAL CONVECTION

To evaluate effects of fins on heat removal properties, modeling of transport packages on heat flow analysis was studied.
Results of temperature measurement on simulated part of a transport package and results of heat flow analysis using FLUENT code were compared.