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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.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Brazilian National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Brazilian National Report
On 29 September 1997 the Join Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management was open for signature at the headquarters of the International Atomic Energy Agency in Vienna. Brazil signed the Convention on October 11th, 1997 and ratified it by the Legislative Decree n. 1.019 of November 14th, 2005. Brazil deposited the instrument of ratification with the Depositary on 17 February 2006. The Convention objectives are to achieve and maintain a high level of nuclear safety worldwide in spent fuel and radioactive waste management.
National Report of Brazill 2011 for the 4th Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
National Report of Brazill 2011 for the 4th Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
On 29 September 1997, the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management was open for signature at the headquarters of the International Atomic Energy Agency in Vienna. Brazil signed the Convention on October 11th, 1997 and ratified it by the Legislative Decree 1019 of November 14th, 2005. Brazil deposited the instrument of ratification with the Depositary on 17 February 2006.
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.