Category of Content
Siting Experience Documents Only
Publication Date
Country
Keywords
Geochemistry Model Validation Report: Material Degradation and Release Model
Geochemistry Model Validation Report: Material Degradation and Release Model
The purpose of the material degradation and release (MDR) model is to predict the fate of the waste package materials, specifically the retention or mobilization of the radionuclides and the neutron-absorbing material as a function of time after the breach of a waste package during the 10,000 years after repository closure. The output of this model is used directly to assess the potential for a criticality event inside the waste package due to the retention of the radionuclides combined with a loss of the neutron-absorbing material.
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
General Corrosion and Localized Corrosion of Waste Package Outer Barrier
General Corrosion and Localized Corrosion of Waste Package Outer Barrier
The purpose and scope of this model report is to document models for general and localized corrosion of the waste package outer barrier (WPOB) to be used in evaluating long-term waste package performance in the total system performance assessment (TSPA). The waste package design for the license application is a double-wall waste package placed underneath a protective drip shield (SNL 2007 [DIRS 179394]; SNL 2007 [DIRS 179354]). The WPOB will be constructed of Alloy 22 (UNS N06022) (SNL 2007 [DIRS 179567], Section 4.1.1.6), a highly corrosion-resistant nickel-based alloy.
Stress Corrosion Cracking of Waste Package Outer Barrier and Drip Shield Materials
Stress Corrosion Cracking of Waste Package Outer Barrier and Drip Shield Materials
Stress corrosion cracking (SCC) is one of the most common corrosion-related causes for premature breach of metal structural components. SCC is the initiation and propagation of cracks in structural components due to three factors that must be present simultaneously (Jones 1992 [DIRS 169906], Section 8.1): metallurgical susceptibility, critical environment, and sustained tensile stresses.
In-Package Chemistry Abstraction
In-Package Chemistry Abstraction
This report was developed in accordance with the requirements in Technical Work Plan for Postclosure Waste Form Modeling (BSC 2005 [DIRS 173246]). The purpose of the in-package chemistry model is to predict the bulk chemistry inside of a breached waste package and to provide simplified expressions of that chemistry as a function of time after breach to Total Systems Performance Assessment for the License Application (TSPA-LA).
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.
Analysis of Dust Deliquescence for FEP Screening
Analysis of Dust Deliquescence for FEP Screening
The purpose of this report is to evaluate the potential for penetration of the Alloy 22 (UNS N06022) waste package outer barrier by localized corrosion due to the deliquescence of soluble constituents in dust present on waste package surfaces. The results support a recommendation to exclude deliquescence-induced localized corrosion (pitting or crevice corrosion) of the outer barrier from the total system performance assessment for the license application (TSPA-LA).
General Corrosion and Localized Corrosion of the Drip Shield
General Corrosion and Localized Corrosion of the Drip Shield
The repository design includes a drip shield (BSC 2004 [DIRS 168489]) that provides protection for the waste package both as a barrier to seepage water contact and a physical barrier to potential rockfall.
The purpose of the process-level models developed in this report is to model dry oxidation, general corrosion, and localized corrosion of the drip shield plate material, which is made of Ti Grade 7. This document is prepared ·according to Technical Work Plan For: Regulatory Integration Modeling and Analysis of the Waste Form and Waste Package (BSC 2004 [DIRS 171583]).
Analysis of Mechanisms for Early Waste Package / Drip Shield Failure
Analysis of Mechanisms for Early Waste Package / Drip Shield Failure
The purpose of this analysis is to evaluate the types of defects or imperfections that could occur in a waste package or a drip shield and potentially lead to its early failure, and to estimate a probability of undetected occurrence for each type. An early failure is defined as the through-wall penetration of a waste package or drip shield due to manufacturing or handling-induced defects, at a time earlier than would be predicted by mechanistic degradation models for a defect-free waste package or drip shield.
Hydrogen-Induced Cracking of the Drip Shield
Hydrogen-Induced Cracking of the Drip Shield
Hydrogen-induced cracking is characterized by the decreased ductility and fracture toughness of a material due to the absorption of atomic hydrogen in the metal crystal lattice. Corrosion is the source of hydrogen generation. For the current design of the engineered barrier without backfill, hydrogen-induced cracking may be a concern because the titanium drip shield can be galvanically coupled to rock bolts (or wire mesh), which may fall onto the drip shield, thereby creating conditions for hydrogen production by electrochemical reaction.
Analysis of Dust Deliquescence for FEP Screening
Analysis of Dust Deliquescence for FEP Screening
The purpose of this report is to evaluate the potential for penetration of the Alloy 22 (UNS N06022) waste package outer barrier by localized corrosion due to the deliquescence of soluble constituents in dust present on waste package surfaces. The results support a recommendation to exclude deliquescence-induced localized corrosion (pitting or crevice corrosion) of the outer barrier from the total system performance assessment for the license application (TSPA-LA).
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