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DOE’s Centralized Storage Design Alternatives and Security Regulations
DOE’s Centralized Storage Design Alternatives and Security Regulations
Slides - World Institute for Nuclear Security (WINS), Security of Dry Storage of Spent Nuclear Fuel, Vilnius, Lithuania, June 10-12, 2014
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, Second National Report of Lithuania in Accordance with Article 32 of the Convention
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Second National Report of Lithuania in Accordance with Article 32 of the Convention
Lithuania has signed this Convention on 30 September 1997 and ratified it on 18 December 2003. This Convention entered in force in Lithuania on 14 June 2004. This is the second report of Lithuania for this Convention. The aim of the report is to give the information on the fulfillment of obligations of this Convention to other Contracting Parties. This report will be discussed in the Third Review Meeting to be held in Vienna on 11-22 May 2009. This report was prepared according the Guidelines Regarding the Form and Structure of National Reports.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Third National Reort of Lithuania in accordance with Article 32 of the Convention
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Third National Reort of Lithuania in accordance with Article 32 of the Convention
Lithuania has signed this Convention on 30 September 1997 and ratified it on 18 December 2003. This Convention entered in force in Lithuania on 14 June 2004. This is the third report of Lithuania for this Convention. The aim of the report is to give the information on the fulfillment of obligations of this Convention to other Contracting Parties. This report will be discussed in the Third Review Meeting to be held in Vienna on 14-23 May 2012. This report was prepared according the Guidelines Regarding the Form and Structure of National Reports.
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.