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Disposal of Spent Nuclear Fuel and High-level Radioactive Waste
Disposal of Spent Nuclear Fuel and High-level Radioactive Waste
The characteristics of spent nuclear fuel and high-level waste are described, and options for permanent disposal that have been considered are described. These include:
•disposal in a mined geological formation,
•disposal in a multinational repository, perhaps on an unoccupied island,
•by in situ melting, perhaps in underground nuclear test cavities,
•sub-seabed disposal,
•disposal in deep boreholes,
•disposal by melting through ice sheets or permafrost,
•disposal by sending the wastes into space, and
External Criticality Risk of Immobilized Plutonium Waste Form in a Geologic Repository
External Criticality Risk of Immobilized Plutonium Waste Form in a Geologic Repository
This technical report provides an updated summary of the waste package (WP) external criticalityrelated
risk of the plutonium disposition ceramic waste form, which is being developed and
evaluated by the Office of Fissile Materials Disposition of the U.S. Department of Energy (DOE).
The ceramic waste form consists of Pu immobilized in ceramic disks, which would be embedded
in High-Level Waste (HLW) glass in the HLW glass disposal canisters, known as the "can-incanister"
Disposal Criticality Analysis for Aluminum-based Fuel in a Codisposal Waste Package - ORR and MIT SNF - Phase II
Disposal Criticality Analysis for Aluminum-based Fuel in a Codisposal Waste Package - ORR and MIT SNF - Phase II
The objective of this analysis is to characterize the criticality safety aspects of a degraded Department of Energy spent nuclear fuel (DOE-SNF) canister containing Massachusetts Institute of Technology (MIT) or Oak Ridge Research (ORR) fuel in the Five-Pack Defense High-Level Waste (DHLW) waste package to demonstrate concept viability related to use in the Mined Geologic Disposal System (MGDS) environment for the postclosure time frame.
STUK to Review the Safety of Posiva's Final Disposal Facility
STUK to Review the Safety of Posiva's Final Disposal Facility
Press release by STUK stating that it will be reviewing Posiva Oy's license application for constructing a repository for disposal of spent nuclear fuel.
Selecting the Site: The Final Disposal at Olkiluoto
Selecting the Site: The Final Disposal at Olkiluoto
Posiva webpage discussing selecting the site for final disposal of spent fuel.
The Finnish Nuclear Waste Management Programme: Experience, Status and Views on the Future
The Finnish Nuclear Waste Management Programme: Experience, Status and Views on the Future
Presentation by Posiva Oy at The Stockholm Talks on October 2, 2013 on the status of the Finnish nuclear waste management program.
Delay in Finnish Repository Licence Review
Delay in Finnish Repository Licence Review
The Finnish nuclear regulator needs another six months to review Posiva's application to build a waste encapsulation plant and a final repository at Olkiluoto.
Radioactive Waste Management Programmes in OECD/NEA Member Countries: Czech Republic
Radioactive Waste Management Programmes in OECD/NEA Member Countries: Czech Republic
A summary of the radioactive waste management programs in the Czech Republic, including information on nuclear energy; sources, types, and quantities of waste; radioactive waste management policies and programs; research and development; decommissioning and dismantling policies and projects; transport; competent authorities; and financing.
Radioactive Waste Management Programmes in OECD/NEA Member Countries: Spain
Radioactive Waste Management Programmes in OECD/NEA Member Countries: Spain
A summary of the radioactive waste management programs in Spain, including the national nuclear energy context; sources, types, and quantities of waste; radioactive waste management policies and programs; research and development; decommissioning and dismantling policies and projects; transport; authorities and implementing organizations; financing; and public information.
Technical Basis Report For Surface Characteristics, Preclosure Hydrology, And Erosion
Technical Basis Report For Surface Characteristics, Preclosure Hydrology, And Erosion
This study presents a synthesis of information and interpretations relevant to surficial processes at the Yucca Mountain Site. The report is part of the technical basis which will be used to evaluate the suitability of Yucca Mountain, Nevada, as a site for a mined geologic repository for the permanent disposal of high-level radioactive waste and spent nuclear fuel. It provides a description of the surface characteristics, preclosure hydrology, and erosion at the Yucca Mountain Site. This report will provide the technical basis to evaluate three technical guidelines from the U.S.