DEVELOPMENT OF PREDICTION SYSTEM OF DOSE EQUIVALENT RATE AROUND A PACKAGE

Year
1992
Author(s)
Tetsuya Nakao - Kansai Electric Power, Co, Inc.
Goro Minakami - Kansai Electric Power, Co, Inc.
Hiroaki Taniuchi - Kobe Steel Ltd
Kyosuke Fujisawa - Kobe Steel, Ltd. Kobe, Japan
Yukio Matsukawa - CRC Research Institute, Inc.
S. Mimura - CRC Research Institute, Inc.
File Attachment
1509.PDF1.75 MB
Abstract
Spent fuels have had to be transported from nuclear reactor to reprocessing factory. As it is increasingly the high-bum-up type of spent fuel that is being transported, it becomes more and more important to learn how to keep the radiation dose equivalent rate surrounding the fuel package as low as possible, for the purpose of reducing the effects of exposure on the operators that work with the packages. It is therefore necessary first to develop a new system that can evaluate the radiation strength of the source in detail, on the basis of the irradiation history of each fuel assembly in a TN-12 or 12A package, and then to determine the best way to organize the assemblies in the package so that the dose equivalent rate around a package is kept to a minimum.