Numerical simulation of impact problems applied to development of spent fuel transport cask for research reactors

By Quintana F  

Packaging, Transport, Storage and Security of Radioactive Material, Vol. 23, Iss. 1-2, 2012-03 ,pp. : 8-15

Maney Publishing

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Dynamic and quasi-static FE calculation of impact from 9 metre drop of spent fuel transport cask

By Qiao L.   Neumann M.   Komann S.   Ballheimer V.  

Packaging, Transport, Storage and Security of Radioactive Material, Vol. 20, Iss. 4, 2009-12 ,pp. : 174-178

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TN-68 spent fuel transport cask analytical evaluation for drop events

By Shah M. J.   Klymyshyn N. A.   Adkins H. E.   Koeppel B. J.  

Packaging, Transport, Storage and Security of Radioactive Material, Vol. 18, Iss. 1, 2007-03 ,pp. : 11-18

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Spent fuel transport using cask loaded outside pool

By Nasta M.   Quintiliani R.   Brusa L.   Di Gasbarro F.   Gili M.  

Packaging, Transport, Storage and Security of Radioactive Material, Vol. 19, Iss. 3, 2008-09 ,pp. : 135-141

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Thermal analysis of a storage cask for 24 spent PWR fuel assemblies

By Lee J.-C.   Kim D.-H.   Bang K.-S.   Seo K.-S.   Choi B.-I.   Lee H.-Y.  

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