Category of Content
Siting Experience Documents Only
Publication Date
Country
Keywords
Dissolved Concentration Limits of Elements with Radioactive Isotopes
Dissolved Concentration Limits of Elements with Radioactive Isotopes
The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments.
EQ6 calculations for Chemical Degradation of Navy Waste Packages
EQ6 calculations for Chemical Degradation of Navy Waste Packages
The Monitored Geologic Repository Waste Package Operations 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 Navy (Refs. 1 and , 2). The Navy SNF has been considered for disposal at the potential Yucca Mountain site. For some waste packages, the containment may breach (Ref. 3), allowing the influx of water. Water in the waste package may moderate neutrons, increasing the likelihood of a criticality event within the waste package.
Radioactive Waste Repositories and Host Regions: Envisaging the Future Together Synthesis of the FSC National Workshop and Community Visit Bar-le-Duc, France
Radioactive Waste Repositories and Host Regions: Envisaging the Future Together Synthesis of the FSC National Workshop and Community Visit Bar-le-Duc, France
The 7th Forum on Stakeholder Confidence (FSC) National Workshop and Community Visit was held on 7-9 April 2009 in Bar-le-Duc, France. It was organized with teh assistance of the CLIS (the Local Information and Oversight Committee) and the financial and logistical support of Andra, France's National Agency for the Management of Radioactive Waste.
STAKEHOLDER CONFIDENCE AND RADIOACTIVE WASTE DISPOSAL Inauguration, First Workshop and Meeting of the NEA Forum on Stakeholder Confidence in the Area of Radioactive Waste Management
STAKEHOLDER CONFIDENCE AND RADIOACTIVE WASTE DISPOSAL Inauguration, First Workshop and Meeting of the NEA Forum on Stakeholder Confidence in the Area of Radioactive Waste Management
The aim of the Forum’s first workshop was to establish contacts amongst Forum participants and
to lay the basis of its future programme and methods of work. In order to give guidance to the FSC
and, at the same time, to give this initiative high-level input and visibility, the workshop was preceded
by a half-day inaugural event. Members of the NEA Radioactive Waste Management Committee and
invited speakers provided their perspectives in the area of stakeholder confidence. Over the following
EQ6 Calculations for Chemical Degradation of Enrico Fermi Spent Nuclear Fuel Waste Packages
EQ6 Calculations for Chemical Degradation of Enrico Fermi 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 Emico Fermi Atomic Power Plant (Ref. 1). The Fermi fuel has been considered for disposal at the potential Yucca Mountain site.
EQ6 Calculations for Chemical Degradation of Fast Flux Test Facility (FFTF) Waste Packages
EQ6 Calculations for Chemical Degradation of Fast Flux Test Facility (FFTF) Waste Packages
Fuel from the Fast Flux Test Facility ' (FFTF) has been considered for disposal at the proposed
Radioactive Waste Repositories and Host Regions: Envisaging the Future Together
Radioactive Waste Repositories and Host Regions: Envisaging the Future Together
The 7th Forum on Stakeholder Confidence (FSC) National Workshop and Community Visit was held on 7-9 April 2009 in Bar-le-Duc, France.
EQ6 Calculations for Chemical Degradation of TRIGA Codisposal Waste PacKages
EQ6 Calculations for Chemical Degradation of TRIGA Codisposal Waste PacKages
The Monitored Geologic Repository Waste Package Operations 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 Training, Research, Isotopes, General Atomics (TRIGA) reactor (Ref. 1). The TRIGA SNF has been considered for disposal at the potential Yucca Mountain site.
EQ6 Calculation for Chemical Degradation of Shippingport LWBR (Th/U Oxide) Spent Nuclear Fuel Waste Packages
EQ6 Calculation for Chemical Degradation of Shippingport LWBR (Th/U Oxide) Spent Nuclear Fuel Waste Packages
The Monitored Geologic Repository (MGR) Waste Package Department 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 Light Water Breeder Reactor (LWBR) (Ref. 1). The Shippingport LWBR SNF has been considered for disposal at the potential Yucca Mountain site.
Postclosure Analysis of the Range of Design Thermal Loadings
Postclosure Analysis of the Range of Design Thermal Loadings
This report presents a two-phased approach to develop and analyze a “thermal envelope” to represent the postclosure response of the repository to the anticipated range of repository design thermal loadings. In Phase 1 an estimated limiting waste stream (ELWS) is identified and analyzed to determine the extremes of average and local thermal loading conditions. The coldest thermal loading condition is represented by an emplacement drift loaded exclusively with high-level radioactive waste (HLW) and/or defense spent nuclear fuel (DSNF).
Qualification of Thermodynamic Data for Geochemical Modeling of Mineral–Water Interactions in Dilute Systems
Qualification of Thermodynamic Data for Geochemical Modeling of Mineral–Water Interactions in Dilute Systems
This report is developed from Technical Work Plan for: Thermodynamic Databases for Chemical Modeling (BSC 2006 [DIRS 177885]). The purpose of this analysis report is to update the thermochemical database data0.ymp.R4 (Output DTN: SN0410T0510404.002). Various data have been added, corrected, or corroborated, partly in response to four Condition Reports (CRs): CR 6489, CR 6731, CR 7542, and CR 7756. The most notable changes are a general revision of phosphate data to achieve consistency with the recommendations from the Committee on Data for Science and Technology (CODATA) (Cox. et al.
In-Drift Precipitates/Salts Model
In-Drift Precipitates/Salts Model
This report documents the development and validation of the in-drift precipitates/salts (IDPS) process model. The IDPS process model is a geochemical model designed to predict the postclosure effects of evaporation and deliquescence on the chemical composition of water within the Engineered Barrier System (EBS) in support of the total system performance assessment (TSPA). Application of the model in support of TSPA is documented in Engineered Barrier System: Physical and Chemical Environment (BSC 2005 [DIRS 175083]).
Engineered Barrier System: Physical and Chemical Environment
Engineered Barrier System: Physical and Chemical Environment
The purpose of this model report is to describe the evolution of the physical and chemical environmental conditions within the waste emplacement drifts of the repository, including the drip shield and waste package surfaces. This report documents the development of a new process-level model, the near-field chemistry (NFC) model, and develops two abstraction models.
Local Liaison Committees and National Association of Local Liaison Committees: the French experience
Local Liaison Committees and National Association of Local Liaison Committees: the French experience
In the context of the governance of nuclear activities, especially in the field of the radioactive waste management, the self-structuring of civil society is a necessary condition of the citizens’ action. The experience of French “Commissions Locales d’Information” (CLIs) and their national federation the “Association Nationale des Commissions Locales d’Information” (ANCLI) represent an interesting and original example of local actors empowerment. In France, Local Information Commissions (CLI) are attached to most of the nuclear sites.
Making Nuclear Waste Governable: Deep Underground Disposal and the Challenge of Reversibility
Making Nuclear Waste Governable: Deep Underground Disposal and the Challenge of Reversibility
This book is the result of a collaboration that began over two years ago between researchers from the social sciences and Andra engineers and natural scientists. Contributions to the various chapters have been discussed and enhanced, especially during the workshop and the interdisciplinary conference both held by Andra in 2008 and 2009<br>respectively.
WP 2 Appendix 3 Local independent expertise as a mechanism of influence on national policy processes: the independent assessment of ANDRA’s research programme led by the IEER on request of the CLIS of Bure.
WP 2 Appendix 3 Local independent expertise as a mechanism of influence on national policy processes: the independent assessment of ANDRA’s research programme led by the IEER on request of the CLIS of Bure.
The case study presented in this document was carried out in the framework of the second work package (influence of local actors on national decision-making processes) of the European research project COWAM 2. The study aims at analysing the process of independent assessment of the research programme of the French National Radioactive Waste Management Agency (ANDRA), commissioned to the Institute for Energy and Environmental Research (IEER) by the Local Committee of Information and Monitoring (CLIS) associated to the underground research laboratory of Bure.
ANDRA The french national radioactive waste management agency
ANDRA The french national radioactive waste management agency
Waste management operation began in France in 1969. Created in 1979 as an agency within the CEA, ANDRA was established by the December 1991 Waste Act as an independent public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministries in charge of Energy, Ecology, and Research. Its 3 basic missions were extended and their funding secured through the 2006 Planning Act (www.andra.fr).
WP 2 Appendix 2 The influence of the local community of Dunkirk on the process of elaboration of the 30th July 2003 Law for the prevention of natural and technological risks
WP 2 Appendix 2 The influence of the local community of Dunkirk on the process of elaboration of the 30th July 2003 Law for the prevention of natural and technological risks
This case study was carried out in the framework of the second work package (influence of local actors on national decision-making processes) of the European research project COWAM 2. The study aims at identifying and analysing the strategies and influence mechanisms implemented by the local actors of Dunkirk in order to influence the process of elaboration of the 30th July Law on the prevention of natural and technological risks. This case study was carried out using, on the one hand, a desk study and, on the other hand, a participative methodology involving a working group.
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).
Substainable Territorial Development Associated with Radioactive Waste Management
Substainable Territorial Development Associated with Radioactive Waste Management
This research brief presents the economic development associated with the laboratory for a deep geological repository for high activity radioactive waste situated in the municipality of Bure. It has been described in the framework of the first topic in the project COWAM In Practice (CIP), i.e. the sustainable territorial development associated with radioactive waste management.
D1-8 Prospective Case Study - France
D1-8 Prospective Case Study - France
Sustainable Development Report: Managing Today to Prepare for Tomorrow
Sustainable Development Report: Managing Today to Prepare for Tomorrow
Andras goal of Sustainability
France - Fourth National Report on Compliance with the Joint Convention Obligations, Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
France - Fourth National Report on Compliance with the Joint Convention Obligations, Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
This report is established by France in accordance with Article 32 of the Joint Convention on the implementation of<br/>the obligations of the Joint Convention. It presents more<br/>particularly the latest developments in the management of<br/>spent fuel and radioactive waste in France in the<br/>framework of the fourth review meeting of the Joint<br/>Convention.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Third Review Meeting, Questions Asked to France and Answers
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Third Review Meeting, Questions Asked to France and Answers
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Third Review Meeting, Questions Asked to France and Answers