Experimental and Analytical Study for Demonstration Program on Shielding of Casks for High-Level Wastes

Year

1992

Author(s)

K. Ueki - Ship Research Institute, Japan

M. Nakazawa - Department of Nuclear Engineering, University of Tokyo

S. Hattori - Central Research Institute of Electric Power Industry

S. Ozaki - Central Research Institute of Electric Power Industry

H. Tamaki - Central Research Institute of Electric Power Industry, Japan

H. Kadotani - CRC Research Institute, Inc.

T. Ishuzuka - CRC Research Institute, Inc.

S. Ishikawa - CRC Research Institute, Inc.

File Attachment

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Abstract

As a part of the safety demonstration tests imposed on a cask for high-level wastes, shielding experiments have been performed at the Central Research Institute of Electric Power Industry (CRIEPI) under contract with the Science and Technology Agency (STA) of Japan. The objective of the study is to validate the shielding ability of the demonstration-test cask for high-level wastes transport and to decide whether or not the cask is satisfied with the dose levels prescribed by the IAEA safe transport regulations (IAEA 1985). The cask provided for the demonstration tests was designed to contain twenty eight canisters for vitrified high-level wastes. The main shield for gamma rays is a thick carbon steel, and for neutrons a thick silicone rubber layer. Outside of the silicone rubber, a thin carbon steel layer covers it completely to shield secondary gamma rays mainly produced in it.