The main objective of this study is to establish the analysis and test technologies to evaluate the integrity and safety of the KSC-7 spent fuel shipping cask and to develop highly effective neutron shielding materials for the transportation cask. The main contents of this report are as follows. - Structural, radiation shielding, heat transfer, and criticality analysis - The structural integrity tests by using 1/3 scale models and the thermal tests by 0.5 m slice model - The development of silicone rubber based neutron shielding materials 27 refs., 32 figs., 38 tabs.
Development of spent fuel transportation technology
1994
139 pages
Report
No indication
English
Spent Fuel Transportation Problems
NTIS | 1977
|Intermodal Transportation of Spent Fuel
NTIS | 1983
|Probability of Spent Fuel Transportation Accidents
NTIS | 1981
|