Demonstration Test for Transporting Vitrified High-Level Radiooctive Waste* - 0.3m Free-Drop Test

Year
1992
Author(s)
C. Ito - Central Research Institute of Electric Power Industry (CRIEPI)
O. Kato - Central Research Institute of Electric Power Industry
Y. Kato - Central Research Institute of Electric Power Industry
File Attachment
1060.PDF1.24 MB
Abstract
The object of this demonstration test program is to ensure safe transport of vitrified highlevel radioactive wastes resulting from the reprocessing plants of cx:x.J.EMA at La Hague and of BNFL at Sellafield, and which will be returned to Japan according to the contracts signed by the reprocessors with Japanese utilities. A test cask for shipping high -level radioactive wastes was designed and fabricated [ Tamaki et al ] . The cask was then subjected to the series of tests stipulated by the IAEA regulation. This paper describes the results of a 0.3m free- drop test and simulation analysis by FEM analysis.