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.


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    Title :

    Development of spent fuel transportation technology


    Contributors:
    J. B. Doh (author) / H. Y. Kang (author) / K. S. Suh (author) / C. Y. Baek (author) / J. H. Yoon (author)

    Publication date :

    1994


    Size :

    139 pages


    Type of media :

    Report


    Type of material :

    No indication


    Language :

    English






    Spent Fuel Transportation Problems

    A. N. Kondrat'ev / Y. A. Kosarev / E. A. Yulikov | NTIS | 1977