Containment integrity evaluation of MSF-type cask for interim storage and transport of PWR spent fuel

Author:

Saito Yoshiyuki,Kishimoto Junichi,Matsuoka Toshihiro,Tamaki Hiroki,Kitada Akio

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference9 articles.

1. Regulations for the safe transport of radioactive material. IAEA safety standards series No. TS-R-1. 2009 Edition.

2. Ichihashi T, Ishiko D, Ogawa A, Morishima M. Verification tests of neutron shielding materials and shielding assessment. Proceedings of the 15th International Symposium on the Packaging and Transportation of Radioactive materials 2007.

3. Maeguchi T, Kamiwaki Y, Ishiko D, Yamamoto T. Development and reliability verification of aluminum alloys for basket of transport and storage cask for spent nuclear fuel. Proc. Proceedings of the 15th International Symposium on the Packaging and Transportation of Radioactive materials 2007.

4. Tamaki H, Kimura T, Hode S, Kishimoto J, Yamamoto T. Structural integrity of MSF-57BG Transport and storage cask based on full-scale and 1/2.5-scale drop test results. Proceedings of the 15th International Symposium on the Packaging and Transportation of Radioactive materials 2007.

5. Kishimoto J, Kitada A, Nishizaki C, Saito Y. Dependency of temperature on wooden materials’ mechanical property and effect of impact energy absorption of shock absorbers. Proceedings of the 15th International Symposium on the Packaging and Transportation of Radioactive materials 2007.

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