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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
Regional Geological Assessment of the Devonian-Mississippian Shale Sequence of the Appalachian, Illinois, and Michigan Basins relative to Potential Storage/Disposal of Radioactive Wastes
Regional Geological Assessment of the Devonian-Mississippian Shale Sequence of the Appalachian, Illinois, and Michigan Basins relative to Potential Storage/Disposal of Radioactive Wastes
The thick and regionally extensive sequence of shales and associated clastic sedimentary rocks of Late Devonian and Early Mississippian age has been considered among the “nonsalt geologies” for deep subsurface containment of high-level radioactive wastes.
Spent-Fuel Test - Climax: An Evaluation of the Technical Feasibility of Geologic Storage of Spent Nuclear Fuel in Granite
Spent-Fuel Test - Climax: An Evaluation of the Technical Feasibility of Geologic Storage of Spent Nuclear Fuel in Granite
This summary volume outlines results that are covered in more detail in the final report of the Spent-Fuel Test-Climax project. The project was conducted between 1978 and 1983 in the granite Climax stock at the Nevada Test Site. Results indicate that spent fuel can be safely stored for periods of years in this host medium and that nuclear waste so emplaced can be safely retrieved. We also evaluated the effects of heat and radiation (alone and in combination) on emplacement canisters and the surrounding rock mass.
Public Values and Stakeholder Involvement - A New Framework for Performance Assessment
Public Values and Stakeholder Involvement - A New Framework for Performance Assessment
The objective of the RISCOM II project is to share the knowledge of the context of radioactive waste management in various European countries and to see to what extent it is possible to apply more widely the RISCOM Model (Andersson et al., 1998) in order to improve the acceptability of radioactive waste management. Thus, the project aims to promote the development of processes involving transparency, as well as means involving greater participation of the public.
Review of initiatives addressing socio-technical challenges of RWM & geological disposal in international programmes
Review of initiatives addressing socio-technical challenges of RWM & geological disposal in international programmes
Reflecting on the Implementing Geological Disposal Technology Platform as a knowledge network and potential scenarios for stakeholder involvement
Reflecting on the Implementing Geological Disposal Technology Platform as a knowledge network and potential scenarios for stakeholder involvement
This report was prepared in the context of Work Package 3 of the InSOTEC project. The overall objective of this work package (WP) is to take a closer look at arenas where socio-technical combinations on radioactive waste management (RWM) are formed. The attempt is to illustrate the interconnections between the sources of different types of information and knowledge development with the various stakeholders having access to that information.
DHLW Glass Waste Package Criticality Analysis (SCPB: N/A)
DHLW Glass Waste Package Criticality Analysis (SCPB: N/A)
This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to determine the viability of the Defense High-Level Waste (DHLW) Glass waste package concept with respect to criticality regulatory requirements in compliance with the goals of the Waste Package Implementation Plan (Ref. 5.1) for conceptual design. These design calculations are performed in sufficient detail to provide a comprehensive comparison base with other design alternatives.
Criticality Evaluation of Degraded Internal Configurations for a 44 BWR Waste Package
Criticality Evaluation of Degraded Internal Configurations for a 44 BWR Waste Package
The purpose of this calculation is to perform an example criticality evaluation for degraded internal configurations of a boiling water reactor (BWR) waste package (WP) containing 44 spent nuclear fuel (SNF) assemblies.
EQ6 Calculation for Chemical Degradation of Shippingport PWR (HEU Oxide) Spent Nuclear Fuel Waste Packages
EQ6 Calculation for Chemical Degradation of Shippingport PWR (HEU Oxide) Spent Nuclear Fuel Waste Packages
The Monitored Geologic Repository (MGR) Waste Package Operations (WPO) of the Civilian Radioactive Waste Management System Management & Operating Contractor (CRWMS M&O) performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Shippingport Pressurized Water Reactor (PWR) (Ref. 1). The Shippingport PWR SNF has been considered for disposal at the proposed Yucca Mountain site.
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''.
Republic of Hungary National Report, Second Report, prepared in the Framework on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
Republic of Hungary National Report, Second Report, prepared in the Framework on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
The Republic of Hungary was among the first to sign the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (hereafter Convention), established under the auspices of the International Atomic Energy Agency, on 29 September 1997, and ratified it on 2 June 1998. The Convention was promulgated in Act LXXVI of 2001. In order to fulfill the obligations of Article 32 of the Convention the present National Report has been prepared and submitted.
Republic of Hungary National Report, Document prepared in the Framework on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, First Report
Republic of Hungary National Report, Document prepared in the Framework on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, First Report
The Republic of Hungary was among the first to sign the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (hereafter Convention), established under the auspices of the International Atomic Energy Agency, on 29th September 1997, and ratified it on 2nd June 1998. The Convention was promulgated in Act LXXVI of 2001. In order to fulfil the obligations of Article 32 of the Convention the present National Report has been prepared and submitted.
Republic of Hungary National Report, Third Report, prepared in the Framework on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
Republic of Hungary National Report, Third Report, prepared in the Framework on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
The Republic of Hungary was among the first to sign the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (hereafter Convention), established under the auspices of the International Atomic Energy Agency, on 29 September 1997, and ratified it on 2 June 1998. The Convention was promulgated by Act LXXVI of 2001 [I.11].
Republic of Hungary National Report, Fourth Report, prepared within the Framework on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
Republic of Hungary National Report, Fourth Report, prepared within the Framework on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (hereafter Convention) was promulgated by Act LXXVI of 2001 [I.11]. (Hereafter the references to legal instruments listed in Annex 4 are used by numbering in brackets.) In order to fulfill the obligations of Article 32 of the Convention the present National Report has been prepared and submitted.
Safety Evaluation of a Geological Repository
Safety Evaluation of a Geological Repository
The Law of 30 December 1991 [1] confers to Andra the mission of assessing the feasibility of a repository of high-level and long-lived (HLLL) waste in a deep geological formation.
DSNF and Other Waste Form Degradation Abstraction
DSNF and Other Waste Form Degradation Abstraction
Several hundred distinct types of DOE-owned spent nuclear fuel (DSNF) may potentially be disposed in the Yucca Mountain repository. These fuel types represent many more types than can be viably individually examined for their effect on the Total System Performance Assessment for the License Application (TSPA-LA). Additionally, for most of these fuel types, there is no known direct experimental test data for the degradation and dissolution of the waste form in repository groundwaters.
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.
1999 Design Basis Waste Input Report for Commercial Spent Nuclear Fuel
1999 Design Basis Waste Input Report for Commercial Spent Nuclear Fuel
The purpose of this document is to provide waste quantity and sequencing information that serves as the design basis for commercial spent nuclear fuel (CSNF) arriving at the repository, and the information on the transportation systems that will be used to deliver this fuel. It is intended as input for waste package and repository design analyses needed to ensure that facilities are flexible enough to be capable of receiving, unloading, handling, and emplacing the amounts and types of CSNF expected for receipt under realistic bounding conditions.
Enhancing the Role of State and Local Governments in America’s Nuclear Future: An Idea Whose Time Has Come
Enhancing the Role of State and Local Governments in America’s Nuclear Future: An Idea Whose Time Has Come
This paper, prepared to aid the Blue Ribbon Commission on America’s Nuclear Future in its
deliberations, includes a discussion of the issues that would be faced in the siting, permitting and
licensing of storage and disposal facilities for the “back end” of the commercial nuclear fuel
cycle and for the Department of Energy’s (DOE) high–level radioactive waste. It discusses the
authority that could be employed by non–federal levels of government in supporting or opposing
Configuration Generator Model
Configuration Generator Model
The Disposal Criticality Analysis Methodology Topical Report prescribes an approach to the methodology for performing postclosure criticality analyses within the monitored geologic repository at Yucca Mountain, Nevada. An essential component of the methodology is the Configuration Generator Model for In-Package Criticality that provides a tool to evaluate the probabilities of degraded configurations achieving a critical state.