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Monitored Retrievable Storage Facility Design Criteria Policy Document - 2nd Draft
Monitored Retrievable Storage Facility Design Criteria Policy Document - 2nd Draft
Nuclear Criticality Calculations for Canister-Based Facilities - DOE SNF
Nuclear Criticality Calculations for Canister-Based Facilities - DOE SNF
The purpose of this calculation is to perform waste-form specific nuclear criticality safety calculations to aid in establishing criticality safety design criteria, and to identify design and process parameters that are potentially important to the criticality safety of Department of Energy (DOE) standardized Spent Nuclear Fuel (SNF) canisters.
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.
Storage of Spent Nuclear Fuel (Specific Safety Guide)
Storage of Spent Nuclear Fuel (Specific Safety Guide)
This Safety Guide provides recommendations and guidance on the storage of spent nuclear fuel. It covers all types of storage facilities and all types of spent fuel from nuclear power plants and research reactors. It takes into consideration the longer storage periods that have become necessary owing to delays in the development of disposal facilities and the decrease in reprocessing activities. It also considers developments associated with nuclear fuel, such as higher enrichment, mixed oxide fuels and higher burnup.
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
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.
Radionuclide Screening
Radionuclide Screening
The waste forms under consideration for disposal in the repository at Yucca Mountain contain scores of radionuclides. It would be impractical and highly inefficient to model all of these radionuclides in a total system performance assessment (TSPA). Thus, the purpose of this radionuclide screening analysis is to remove from further consideration (screen out) radionuclides that are unlikely to significantly contribute to radiation dose to the public from a nuclear waste repository at Yucca Mountain.
Preclosure Consequence Analyses
Preclosure Consequence Analyses
The purpose of this calculation is to demonstrate that the preclosure performance objectives specified in 10 CFR 63.111(a) and 10 CFR 63.111(b) (Reference 2.2.1) have been met for the proposed design and operations in the geologic repository operations area (GROA) during normal operations and Category 1 event sequences, and following Category 2 event sequences. Category 1 event sequences are those natural and human-induced event sequences that are expected to occur one or more times before permanent closure of the repository.
Canister Handling Facility Criticality Safety Calculations
Canister Handling Facility Criticality Safety Calculations
This design calculation revises and updates the previous criticality evaluation for the canister handling, transfer and staging operations to be performed in the Canister Handling Facility (CHF) documented in BSC (Bechtel SAIC Company) 2004 (DIRS 167614).
Nuclear Criticality Calculations for Canister-Based Facilities - Commercial SNF
Nuclear Criticality Calculations for Canister-Based Facilities - Commercial SNF
The purpose of this calculation is to perform waste-form specific nuclear criticality safety calculations to aid in establishing criticality safety design criteria, and to identify design and process parameters that are potentially important to the criticality safety of the transportation, aging and disposal (TAD) canister-based systems.
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.
Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada (40 CFR Part 197) -- Final Rule Response to Comments Document
Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada (40 CFR Part 197) -- Final Rule Response to Comments Document
EPA held a 90-day public comment period for the proposed radiation protection standards for Yucca Mountain (August 27, 1999 through November 26, 1999). Sixty-nine (69) sets of written comments were submitted to EPAÕs Air Docket regarding the proposed standards, although some commenters submitted more than one set of written comments. In addition, the Agency received oral testimony on the proposed standards from 28 speakers during public hearings that were held in Washington, DC; Las Vegas, NV; Amargosa Valley, NV; and Kansas City, MO.
D1-8 Prospective Case Study - France
D1-8 Prospective Case Study - France
Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada; Final Rule
Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada; Final Rule
We, the Environmental Protection Agency (EPA), are promulgating public health and safety standards for radioactive material stored or disposed of in the potential repository at Yucca Mountain, Nevada. Section 801 of the Energy Policy Act of 1992 (EnPA, Pub. L. 102Ð486) directs us to develop these standards. Section 801 of the EnPA also requires us to contract with the National Academy of Sciences (NAS) to conduct a study to provide findings and recommendations on reasonable standards for protection of the public health and safety.
Sustainable Development Report: Managing Today to Prepare for Tomorrow
Sustainable Development Report: Managing Today to Prepare for Tomorrow
Andras goal of Sustainability
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Austrian National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Austrian National Report
This report provides - a detailed description of the Austrian policy and the usual practices concerning the management of spent fuel of the Austrian research reactors and the management of radioactive waste (see Section B); - a detailed description of the Austrian legal regime concerning the management of spent fuel of the Austrian research reactors and the management of radioactive waste (see Section E).
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 Second 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 Second 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 Second National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Czech Republic National Report, Revision 2.3
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Czech Republic National Report, Revision 2.3
. On 25 March 1999 the Government of the Czech Republic approved the Joint Convention which came into effect in the Czech Republic on 18 June 2001. In agreement with the obligations resulting from its accession to the Joint Convention the Czech Republic has already drawn the second National Report for the purposes of Review Meetings of the Contracting Parties, which describes the system of spent fuel and radioactive waste management in the scope required by selected articles of the Joint Convention.