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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
Volumes, Masses, and Surface Areas for Shippingport LWBR Spent Nuclear Fuel in a DOE SNF Canister
Volumes, Masses, and Surface Areas for Shippingport LWBR Spent Nuclear Fuel in a DOE SNF Canister
The purpose of this calculation is to estimate volumes, masses, and surface areas associated with (a) an empty Department of Energy (DOE) 18-inch diameter, 15-ft long spent nuclear fuel (SNF) canister, (b) an empty DOE 24-inch diameter, 15-ft long SNF canister, (c) Shippingport Light Water Breeder Reactor (LWBR) SNF, and (d) the internal basket structure for the 18-in. canister that has been designed specifically to accommodate Seed fuel from the Shippingport LWBR.
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.
Evaluation of Codisposal Viability for Aluminum-Clad DOE-Owned Spent Fuel: Phase I Intact Codisposal Canister
Evaluation of Codisposal Viability for Aluminum-Clad DOE-Owned Spent Fuel: Phase I Intact Codisposal Canister
This evaluation is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to provide analyses of disposal of aluminum (AI)-based Department of Energy-owned research reactor spent nuclear fuel (DOE-SNF) in a codisposal waste package with five canisters of high-level waste (HLW). The analysis was performed in sufficient detail to establish the technical viability of the Al-based DOE-SNF codisposal canister option.
Reversible Bending Fatigue Testing on Zry-4 Surrogate Rods
Reversible Bending Fatigue Testing on Zry-4 Surrogate Rods
Slides - WM2014 Symposia, March 2-6, 2014, Phoenix, AZ
Evaluation of Codisposal Viability for Aluminum-Clad DOE-Owned Spent Fuel: Phase ll Degraded Codisposal Canister Internal Criticality
Evaluation of Codisposal Viability for Aluminum-Clad DOE-Owned Spent Fuel: Phase ll Degraded Codisposal Canister Internal Criticality
This report presents the analysis and conclusions with respect to disposal criticality for canisters containing aluminum-based fuels from research reactors. The analysis has been divided into three phases. Phase I, dealt with breached and flooded waste packages containing relatively intact canisters and intact internal (basket) structures; Phase II, the subject of this report, covers the degradation of the spent nuclear fuel (SNF) and structures internal to the codisposal waste package including high level waste (HLW), canisters, and criticality control material.
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).
UFD Storage and Transportation - Transportation Working Group Report
UFD Storage and Transportation - Transportation Working Group Report
The Used Fuel Disposition (UFD) Transportation Task commenced in October 2010. As its first task, Pacific Northwest National Laboratory (PNNL) compiled a list of structures, systems, and components (SSCs) of transportation systems and their possible degradation mechanisms during extended storage. The list of SSCs and the associated degradation mechanisms [known as features, events, and processes (FEPs)] were based on the list of used nuclear fuel (UNF) storage system SSCs and degradation mechanisms developed by the UFD Storage Task (Hanson et al. 2011).
NUREG-1768 United States Nuclear Regulatory Commisssion Package Performance Study Test Protocals
NUREG-1768 United States Nuclear Regulatory Commisssion Package Performance Study Test Protocals
This test protocols report presents the NRC staff’s preliminary plans for an experimental phase of the Package Performance Study (PPS), which is examining the response of transportation casks to extreme transportation accident conditions. The staff proposes to conduct tests of full-scale rail and full-scale truck casks including a high-speed impact with an unyielding surface followed by an extreme fire test. The NRC has a contract in place with Sandia National Laboratories (SNL) to conduct the impact and fire tests and to carry out a series of analyses to support the test program.
Gap Analysis to Support Extended Storage of Used Nuclear Fuel
Gap Analysis to Support Extended Storage of Used Nuclear Fuel
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<p><span style="font-size: 12.000000pt; font-family: 'TimesNewRomanPSMT'">This report fulfills the M1 milestone M11UF041401, “Storage R&D Opportunities Report” under Work Package Number FTPN11UF0414. </span></p>
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
OECD/NEA: France
OECD/NEA: France
Identifying remaining socio-technical challenges at the national level: France
Identifying remaining socio-technical challenges at the national level: France
France isn’t only a country known for its cheese… it’s also a country of nuclear power. With its 58 nuclear reactors (63,000 megawatts), producing 79% of the country’s electricity, France is arguably the world’s leader in the production of nuclear energy. It is estimated that the relative contribution of nuclear energy to power production in France will decline to 70% in 2020 - the main reason for this being governmental investments into renewable energies.