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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.
OECD/NEA: Austria
OECD/NEA: Austria
Radioactive Waste Management and Decommissioning in Austria
Radioactive Waste Management and Decommissioning in Austria
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Austrian National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Austrian National Report
This report provides - a detailed description of the Austrian policy and the usual practices concerning the management of spent fuel of the Austrian research reactors and the management of radioactive waste (see Section B); - a detailed description of the Austrian legal regime concerning the management of spent fuel of the Austrian research reactors and the management of radioactive waste (see Section E).
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Second Austrian National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Second Austrian National Report
In Austria there is neither a nuclear power plant (NPP) nor any other fuel cycle facility in op- eration. One NPP was constructed in Zwentendorf in the 1970s, but, as a consequence of the negative vote in a referendum never put into operation. Two out of three research reactors in Austria have been shut down (ASTRA Seibersdorf in 2000, SIEMENS Argonaut Graz in 2004) and are currently under decommissioning. The remaining TRIGA research reactor in Vienna is still in operation. Spent nuclear fuel is stored on site in wet or dry storage facilities.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Second Review Meeting of the Contracting Parties, 15 to 24 2006, Vienna, Austria, Summary Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Second Review Meeting of the Contracting Parties, 15 to 24 2006, Vienna, Austria, Summary Report
1. Recognizing the importance of the safe management of spent nuclear fuel and radioactive waste, the international community agreed upon the necessity of adopting a convention describing how such safe management could be achieved: this was the origin of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (the “Joint Convention”), which was adopted on 5 September 1997 and entered into force on 18 June 2001. 2.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Third Review Meeting of the Contracting Parties, 11 to 20 May 2009, Vienna, Austria, Summary Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Third Review Meeting of the Contracting Parties, 11 to 20 May 2009, Vienna, Austria, Summary Report
1. Recognizing the importance of the safe management of spent nuclear fuel and radioactive waste, the international community agreed upon the necessity of adopting a convention with the objective of achieving and maintaining a high level of safety worldwide in spent fuel and radioactive waste management: this was the origin of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (the “Joint Convention”), which was adopted on 5 September 1997 and entered into force on 18 June 2001. 2.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Fourth Review Meeting of the Contracting Parties, 14 to 23 May 2012, Vienna, Austria, Final Summary Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Fourth Review Meeting of the Contracting Parties, 14 to 23 May 2012, Vienna, Austria, Final Summary Report
1. Recognizing the importance of the safe management of spent nuclear fuel and radioactive waste, the international community agreed upon the necessity of adopting a convention with the objective of achieving and maintaining a high level of safety worldwide in spent fuel and radioactive waste management: this was the origin of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (the “Joint Convention”), which was adopted on 5 September 1997 and entered into force on 18 June 2001. 2.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, First Review Meeting of the Contracting Parties 3 to 14 November 2003, Vienna, Austria, Summary Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, First Review Meeting of the Contracting Parties 3 to 14 November 2003, Vienna, Austria, Summary Report
1. The operation of nuclear reactors whether for the purposes of electricity production or research, generates spent nuclear fuel and radioactive waste. Other activities also generate radioactive waste. The recognition by the international community of the importance of ensuring the safety of the management of spent fuel and the safety of the management of radioactive waste, led to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Convention).
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.