Radiological aspects and behavior of spent fuel considering long-term storage |
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| Affiliation: | 1. Power & Industrial Systems R&D Center, Power Systems Company, Toshiba Corporation, 4-1, Ukishima-cho, Kawasaki-ku, Kawasaki 210-0862, Japan;2. Isogo Nuclear Engineering Center, Power Systems Company, Toshiba Corporation, 8, Shinsugita-cho, Isogo-ku, Yokohama 235-8523, Japan;1. Faculty of Technical Sciences, University of Novi Sad, Trg Dositeja Obradovica 6, Novi Sad, Serbia;2. Institute of Nuclear Sciences Vinca, University of Belgrade, Belgrade, Postanski fah 522, Serbia;1. Lithuanian Energy Institute (LEI), Breslaujos str. 3, LT-44403 Kaunas, Lithuania;2. Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, Schwertnergasse 1, D-50667 Köln, Germany;1. European Commission, Joint Research Centre (JRC), Institute for Transuranium Elements (ITU), Nuclear Security Unit, Ispra, VA, Italy;2. Department of Biological, Geological and Environmental Sciences—Section of Geology, University of Bologna, Bologna, Italy;3. Department of Industrial Engineering, University of Bologna, Bologna, Italy;4. Department of Chemistry, University of Bologna, Bologna, Italy;1. Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Schwertnergasse 1, 50667 Cologne, Germany;2. VTT Technical Research Centre of Finland, Kemistintie 3, P.O. Box 1000, Espoo FI-02044 VTT, Finland;1. Institut de Radioprotection et de Sûreté Nucléaire, IRSN, Bat. 702, CE Cadarache, BP3-13115 Saint Paul-Lez-Durance Cedex, France;2. Paul Scherrer Institut, CH 5232, Villigen PSI, Switzerland |
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| Abstract: | For spent nuclear fuel management in Germany, the concept of dry interim storage in dual purpose casks before direct disposal is applied. Current operation licenses for storage facilities have been granted for a storage time of 40 years. Due to the current delay in site selection, an extension of the storage time seems inevitable. In consideration of this issue, GRS performed burnup calculations, thermal and mechanical analyses as well as particle transport and shielding calculations for UO2 and MOX fuels stored in a cask to investigate long-term behavior of the spent fuel related parameters and the radiological consequences. It is shown that at the beginning of the dry storage period, cladding hoop stress levels sufficient to cause hydride reorientation could be present in fuel rods with a burnup higher than 55 GWd/tHM. The long-term behavior of the cladding temperatures indicates the possibility of reaching the ductile-to-brittle transition temperature during extended storage scenarios. Surface dose rates are 3 times higher when a cask is partially loaded with 4 MOX fuel assemblies. Due to radioactive decay, long-term storage will have a positive impact on the radiological environment around the cask. |
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| Keywords: | Long-term storage Cladding Temperature Hoop stress Dose rate |
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