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Rail-Cask Tests: Normal-Conditionsof- Transport Tests of Surrogate PWR Fuel Assemblies in an ENSA ENUN 32P Cask

McConnell, Paul E.; Ross, Steven B.; Grey, Carissa A.; Uncapher, William L.; Arviso, Michael A.; Garmendia, Rafael Glez.; Fernandez Perez, Ismael F.; Palacio, Alejandro P.; Calleja, Guillermo C.; Garrido, David G.; Rodriguez Casas, Ana R.; Gonzalez Garcia, Luis G.; Chilton, Lyman W.; Ammerman, Douglas J.; Walz, Jacob W.; Gershon, Sabina G.; Saltzstein, Sylvia J.; Sorenson, Ken S.; Klymyshyn, Nicholas K.; Hanson, Brady D.; Pena, Ruben P.; Walker, Russell W.

This report describes tests conducted using a full-size rail cask, the ENSA ENUN 32P, involving handling of the cask and transport of the cask via truck, ships, and rail. The purpose of the tests was to measure strains and accelerations on surrogate pressurized water reactor fuel rods when the fuel assemblies were subjected to Normal Conditions of Transport within the rail cask. In addition, accelerations were measured on the transport platform, the cask cradle, the cask, and the basket within the cask holding the assemblies. These tests were an international collaboration that included Equipos Nucleares S.A., Sandia National Laboratories, Pacific Northwest National Laboratory, Coordinadora Internacional de Cargas S.A., the Transportation Technology Center, Inc., the Korea Radioactive Waste Agency, and the Korea Atomic Energy Research Institute. All test results in this report are PRELIMINARY – complete analyses of test data will be completed and reported in FY18. However, preliminarily: The strains were exceedingly low on the surrogate fuel rods during the rail-cask tests for all the transport and handling modes. The test results provide a compelling technical basis for the safe transport of spent fuel.

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Transportation operations model analysis for removal of stranded fuel from shutdown reactors

Packaging, Transport, Storage and Security of Radioactive Material

Kalinina, E.A.; McConnell, Paul E.; Busch, I.K.; Maheras, S.J.; Best, R.E.

The transportation operations model was used to identify options for removing stranded fuel currently in dry storage at nine shutdown reactor sites to a hypothetical consolidated storage facility. The logistical variables included the campaign duration, fuel selection priority, consist size and location of the consolidated storage and maintenance facilities. The major factors affecting the logistics of fuel removal were identified. Recommendations for optimal strategies for the transport of stranded fuel from shutdown sites are made.

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Results 1–25 of 47
Results 1–25 of 47