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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.
WP 2 Appendix 5 Participación Institucional De Los Municipios En El Proceso De Toma De Decisiones Para El Emplazamiento De Un Almacenamiento De Residuos Radiactivos
Aspects of Governance in the Practical Implementation of the Concept of Reversibility for Deep Geological Disposal
Aspects of Governance in the Practical Implementation of the Concept of Reversibility for Deep Geological Disposal
The European project COWAM in Practice (CIP) was aimed to lead for three years (2007-2009) a process of monitoring, analyzing and evaluating the governance linked with radioactive waste management. This project, in cooperation with a research group and stakeholders, was conducted in parallel in 5 European countries (Spain, France, United Kingdom, Romania, Slovenia).
D1-11 Prospective Case Study - Spain
D1-11 Prospective Case Study - Spain
WP 2 Appendix 4 Estudio Sociológico Sobre La A.M.A.C. Y El Hecho Nuclear En España
WP 2 Appendix 4 Estudio Sociológico Sobre La A.M.A.C. Y El Hecho Nuclear En España
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, First Spanish National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, First Spanish National Report
The present document constitutes the First National Report of Spain, drawn up in order to meet the requirements of Article 32 of the Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management, adopted in Vienna on 5th September 1997. This Convention, which was signed by Spain on 30th June 1998 and ratified on 11th May 1999, entered into force on 18th June 2001.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Fourth Spanish National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Fourth Spanish National Report
The present document constitutes the Fourth Spanish National Report, submitted in compliance with the requirements of article 32 of the Joint Convention on Safety in the Management of Spent Fuel and Safety in the Management of Radioactive Waste, done in Vienna on September 5th 1997. This report will be examined during the review meeting of the Contracting Parties contemplated in article 30 of this Convention, which will begin in May 2012.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Second Spanish National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Second Spanish National Report
The present document constitutes the Second Spanish National Report, issued in compliance with the requirements of article 32 of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (hereinafter, Joint Convention), made in Vienna on September 5th 1997. This report will be examined during the Review Meeting between the Contracting Parties contemplated in article 30 of the Joint Convention, which is scheduled to start on May 15th 2006. The Ministry of Industry, Tourism and Trade (Span.
Identifying remaining socio-technical challenges at the national level: Spain
Identifying remaining socio-technical challenges at the national level: Spain
On 29 December 2009, the Spanish government launched a site selection process to host a centralised interim storage facility for spent fuel and high-level radioactive waste. It was an unprecedented call for voluntarism among Spanish municipalities to site a controversial facility. Two nuclear municipalities, amongst a total of thirteen municipalities from five different regions, presented their candidatures to host the facility in their territories. For two years the government did not make a decision.
OECD/NEA: Spain
OECD/NEA: Spain
The "COWAM SPAIN" Initiative and the Current Project Under Consideration for a National Interim Storage Facility for Spent Fuel and High Level Waste
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.