Reduction of the Waste Occupied Area by Nuclide Separation and Horizontal Emplacement of the Waste Packages - 20422

Conference · Wed Jul 01 04:00:00 EDT 2020

OSTI ID:23028026

Okamura, Tomohiro; Minari, Eriko; Nakase, Masahiko; Takeshita, Kenji ^[1]; Asano, Hidekazu ^[2]

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1. Laboratory for Advanced Nuclear Energy, Institute of Innovation Research, Tokyo Institute of Technology (Japan)
2. Radioactive Waste Management Funding and Research Center (Japan)

Two of the key objectives for realizing the advanced nuclear fuel cycle are to reduce the volume of high-level radioactive waste and to reduce the foot-print of the geological repository. To achieve these objectives, research and development on nuclide separation technologies is a prerequisite. In this context, it is necessary to consider the vitrification conditions and the design of the geological repository where separation technologies would be implemented to achieve effective reductions in the volume of vitrified waste and the foot-print of the geological repository. In this study, the effects of the vitrification conditions on the number of vitrified waste units and the disposal area were evaluated, based on the assumption that separation of Cs and Sr from the spent nuclear fuel had been performed. In addition, with reference to the design of the geological repository, the impact on the foot-print of the repository for different emplacement methods of the waste packages was examined. As a result, it was clarified that the waste-occupied area could be reduced by horizontal emplacement of the vitrified waste with low heat generation. In addition, it was demonstrated that a low waste-loaded vitrified waste contributed to a reduction in the foot-print of the geological repository in the case of horizontal emplacement, although the number of vitrified waste units increased. (authors)

• Research Organization: WM Symposia, Inc., PO Box 27646, 85285-7646 Tempe, AZ (United States)
• OSTI ID: 23028026
• Report Number(s): INIS-US--21-WM-20422
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
FUEL CYCLE
HEAT
HIGH-LEVEL RADIOACTIVE WASTES
ISOTOPES
POSITIONING
SEPARATION PROCESSES
SPENT FUELS
VITRIFICATION