Demonstration Test for Transporting Vitrified High-Level Radioactive Wastes: Drop Test

Year
1995
Author(s)
C. Ito - Central Research Institute of Electric Power Industry (CRIEPI)
K. Shimamura - Central Research Institute of Electric Power Industry, Japan
Hidetsugu Yamakawa - Central Research Institute of Electric Power Industry
H. Ohnuma - Central Research Institute of Electric Power Industry, Japan
File Attachment
151.PDF1.3 MB
Abstract
The national policy on the nuclear fuel cycle is based on the \"Long-Term Plan for Utilization\" drawn up the Atomic Energy Commission of Japan, and the basic policy on the nuclear fuel cycle is that spent fuels from light-water reactors (LWR) should be reprocessed. In line with this policy, some spent fuels have been reprocessed overseas and high-level radioactive wastes (HLW) have been generated by such reprocessing. Some of the highlevel radioactive wastes have been returned by surface transport. In order to ensure the safe transport of high-level radioactive wastes, demonstration tests stipulated by the IAEA transport regulation were carried out in the Central Research Institute of Electric Power Industry (Tamaki et al.1992). This paper describes the drop test. This work was conducted under a contract from the Science and Technology of Japan.