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Consilidated Storage for Spent Nuclear Fuel from Decommissioned Commerical Sites
Consilidated Storage for Spent Nuclear Fuel from Decommissioned Commerical Sites
United States of America, Third National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
United States of America, Third National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
The United States of America ratified the Joint Convention on the Safety of Spent Fuel<br/>Management and on the Safety of Radioactive Waste Management (Joint Convention) on<br/>April 9, 2003. The Joint Convention establishes an international peer review process among<br/>Contracting Parties and provides incentives for nations to take appropriate steps to bring their<br/>nuclear activities into compliance with general safety standards and practices.
Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg
Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg
Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina First National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina First National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina First National Report
The BRIDGE
The BRIDGE
Viewing Back End of Nuclear Fuel Cycles Synoptically and Comparatively
Viewing Back End of Nuclear Fuel Cycles Synoptically and Comparatively
The United Kingdom's Third National Report on Compliance with the Obligations of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
The United Kingdom's Third National Report on Compliance with the Obligations of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
This report has been prepared by the United Kingdom (UK) to meet the requirement of Article 32 of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (the ‘Joint Convention’). It considers each of the Joint Convention's obligations and explains how the UK addresses them.<br/>The report covers spent fuel management and radioactive waste management facilities as defined in Article 2 of the Joint Convention. For the purposes of this report, the UK has included spent fuel reprocessing as part of the spent fuel management.
Fourth Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canada's Responses to Questions to its Fourth National Report
Fourth Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canada's Responses to Questions to its Fourth National Report
Fourth Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Canada's Responses to Questions to its Fourth National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, The United Kingdom of Great Britain and Northern Ireland, National Report Presentation for the Second Review Meeting, 15th to 24th May 2006, Vienna
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, The United Kingdom of Great Britain and Northern Ireland, National Report Presentation for the Second Review Meeting, 15th to 24th May 2006, Vienna
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, The United Kingdom of Great Britain and Northern Ireland, National Report Presentation for the Second Review Meeting, 15th to 24th May 2006, Vienna, presented by Dr. Mike Weightman and Dr. Joe McHugh
Annual Report 2010 on Radiation and Nuclear Safety in the Republic of Slovenia
Annual Report 2010 on Radiation and Nuclear Safety in the Republic of Slovenia
In 2010, there were no events that posed a serious radiological threat to the population in Slovenia. There were also no particularities in relation to the services of radiation practices and operators of radiation facilities.
The Krško NPP operated without shutdowns and production was interrupted only for the annual outage. In 2010, the power plant produced 5.7 TWh in total and achieved 89.9% availability. The nuclear power plant had no major problems during the September floods, when the Sava river otherwise seriously threatened settlements in Posavje.
Spent Nuclear Fuel: Accumulating Quantities at Commercial Reactors Present Storage and Other Challenges
Spent Nuclear Fuel: Accumulating Quantities at Commercial Reactors Present Storage and Other Challenges
The amount of spent fuel stored on-site at commercial nuclear reactors will continue to accumulate—increasing by about 2,000 metric tons per year and likely more than doubling to about 140,000 metric tons—before it can be moved off-site, because storage or disposal facilities may take decades to develop. In examining centralized storage or permanent disposal options, GAO found that new facilities may take from 15 to 40 years before they are ready to begin accepting spent fuel. Once an off-site facility is available, it will take several more decades to ship spent fuel to that facility.
Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-capacity Cask Designs
Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-capacity Cask Designs
This paper presents an evaluation of the amount of burnup credit needed for high-density casks to
transport the current U.S. inventory of commercial spent nuclear fuel (SNF) assemblies. A prototypic
32-assembly cask and the current regulatory guidance were used as bases for this evaluation.
By comparing actual pressurized-water-reactor (PWR) discharge data (i.e., fuel burnup and initial
enrichment specifications for fuel assemblies discharged from U.S. PWRs) with actinide-only-based
FEDERAL COMMITMENTS REGARDING USED FUEL AND HIGH-LEVEL WASTES
FEDERAL COMMITMENTS REGARDING USED FUEL AND HIGH-LEVEL WASTES
OCRWM National Transportation Plan DOE/RW-0603 Revision 0
OCRWM National Transportation Plan DOE/RW-0603 Revision 0
This Plan outlines the Department of Energy’s (DOE) 2009 strategy and planning for developing and implementing the transportation system required to transport spent nuclear fuel (SNF) and high-level radioactive waste (HLW) from where the material is generated or stored to the proposed repository at Yucca Mountain, Nevada. As such, it is a historical document that reflected the DOE's thinking and/or approach in 2009.
Operational Waste Stream Assumption for TSLCC Estimates
Operational Waste Stream Assumption for TSLCC Estimates
This document provides the background and basis for the operational waste stream used in the 2000 Total System Life Cycle Cost (TSLCC) estimate for the Civilian Radioactive Waste Management System (CRWMS). This document has been developed in accordance with its Development Plan (CRWMS M&O 2000a), and AP-3.11Q, ''Technical Reports''.
TEV Collision with an Emplaced 5-DHLW/DOE SNF Short Co-Disposal Waste Package
TEV Collision with an Emplaced 5-DHLW/DOE SNF Short Co-Disposal Waste Package
The objective of this calculation is to determine the structural response of the 5-DHLW/DOE (Defense High Level Waste/Department of Energy) SNF (Spent Nuclear Fuel) Short Co-disposal Waste Package (WP) when subjected (while in the horizontal orientation emplaced in the drift) to a collision by a loaded (with WP) Transport and Emplacement Vehicle (TEV) due to an over-run. The scope of this calculation is limited to reporting the calculation results in terms of maximum total stress intensities (Sis) in the outer corrosion barrier (dCB).
Evaluation of the Technical Basis for Extended Dry Storage and Transportation of Used Nuclear Fuel – Executive Summary
Evaluation of the Technical Basis for Extended Dry Storage and Transportation of Used Nuclear Fuel – Executive Summary
The U.S. Nuclear Waste Technical Review Board (Board) is tasked by the amendments to the Nuclear Waste Policy Act of 1982 to independently evaluate U. S. Department of Energy (DOE) technical activities for managing and disposing of used nuclear fuel and high-level radioactive waste. This report was prepared to inform DOE and Congress about the current state of the technical basis for extended dry storage1 of used fuel and its transportation following storage.