Simplified Calculation Method for Radiation Dose Under Normal Condition of Transport

Year
1992
Author(s)
N. Watabe - Central Research Institute of Electric Power Industry
S. Ozaki - Central Research Institute of Electric Power Industry
K. Sato - Central Research Service Co.
A. Sugahara - Mitsubishi Research Institute, Inc.
File Attachment
89.PDF1.07 MB
Abstract
In order to estimate radiation dose during transportation of radioactive materials, the following computer codes are available: RADTRAN, INTERTRAN, J-TRAN. Because these codes consist of functions for estimating doses not only under normal conditions but also in the case of accidents, when nuclei may leak and spread into the environment by air diffusion, the user needs to have special knowledge and experience. According to the nuclear cycle plan in Japan, various packages of radioactive materials will be concentrated in one specified area. The estimations of doses will vary according to variations in such parameters as the distribution of the population, the quantity of material transported, activities of contents, the shape of packages, the velocity of transporters, etc.