Development of Heat-Transfer and Thermal-Analysis Code for Radioactive-Material Packages(CRISCAT)

Year
1992
Author(s)
T. Nagashima - Mitsubishi Research Institute Inc.
M. Wataru - Central Research Institute of Electrical Power Industry, 1646 Abiko, Abiko-shi, Chiba-ken 270-1194 Japan
Hidetsugu Yamakawa - Central Research Institute of Electric Power Industry
K. Nakajima - Mitsubishi Research Institute Inc.
File Attachment
1347.PDF1.61 MB
Abstract
There are various structures of packagings for radioactive-materials according to the quantity and nature of the radioactive-material transported. When the thermal analysis is carried out, structures of the packagings and the thermal behavior of the radioactive material become problems. Until now, to solve these problems, various special techniques have been considered. To make heat-transfer and thermal analysis of the packagings for radioactive-materials easy, new analysis code is developed in which various techniques are reflected.