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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.
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).
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).
European Union Contract Number: FP6-036413. Deliverable 23b. Towards Implementation of Transparency and Participation in Radioactive Waste Management Programmes, ARGONA Final Summary Report
European Union Contract Number: FP6-036413. Deliverable 23b. Towards Implementation of Transparency and Participation in Radioactive Waste Management Programmes, ARGONA Final Summary Report
The point of departure for the ARGONA project is that participation and transparency are key elements of effective risk governance and the acronym ARGONA stands for "Arenas for Risk Governance ". Given the overall objectives, ARGONA intended to demonstrate how participation and transparency link to the political and legal systems and how new approaches can be implemented in radioactive waste management programmes.
Attitudes Towards Radioactive Waste in Switzerland
Attitudes Towards Radioactive Waste in Switzerland
European Union Contract Number: FP6-036413. Deliverable 23a. Towards Implementation of Transparency and Participation in Radioactive Waste Management Programmes, ARGONA Final Report
European Union Contract Number: FP6-036413. Deliverable 23a. Towards Implementation of Transparency and Participation in Radioactive Waste Management Programmes, ARGONA Final Report
ARGONA is a project within the European Commission 6th framework programme. The overall objective was to support transparency of decision-making processes in the radioactive waste programmes of the participating countries, and also of the European Union, by means of a greater degree of public participation.
European Union Contract Number: FP6-036413. Deliverable 22. ARGONA Project, Suggested Guidelines for Transparency and Participation in Nuclear Waste Management Programmes
European Union Contract Number: FP6-036413. Deliverable 22. ARGONA Project, Suggested Guidelines for Transparency and Participation in Nuclear Waste Management Programmes
These proposed guidelines are recommendations that have emerged from the European Union Research Project ARGONA (Arenas for Risk Governance), Contract no.: FP6-036413
Strong Local Support for Final Repository
Strong Local Support for Final Repository
Local support in favor of a final repository for spent nuclear in one's own municipality has increased somewhat in both Oskarshamn and Östhammar. This is shown by the annual public opinion poll that was conducted by Synovate on behalf of SKB.
Continuing Cooperation with Two Municipalities
Continuing Cooperation with Two Municipalities
Web page from SKB's website (Swedish Nuclear Fuel and Waste Management Company) discussing the ongoing cooperation between SKB and both Östhammar, where the repository is to be sited, and Oskarshamn, where the encapsulation plant is to be located.
The Cigéo Project: Meuse/Haute-Marne Reversible Geological Disposal Facility for Radioactive Waste
The Cigéo Project: Meuse/Haute-Marne Reversible Geological Disposal Facility for Radioactive Waste
Report prepared by ANDRA, the French National Radioactive Waste Management Agency, for preparing for public debate in 2013.
ANDRA presents the Actions to be Taken Following the Public Debate on the Cigéo Project
ANDRA presents the Actions to be Taken Following the Public Debate on the Cigéo Project
Press release from ANDRA, the French National Agency for Radioactive Waste Management, regarding the changes it will make in the siting process as a result of public debate on the Cigéo Project, disposal of radioactive waste in a deep geologic repository.
Cigéo, the French Geological Disposal Project
Cigéo, the French Geological Disposal Project
Presentation given by François-Michel Gonnot at the Stockholm Talks on October 2, 2013 regarding Cigéo, the French Geological Disposal Project.
Annual Sustainable Development and Activity Report - 2011
Annual Sustainable Development and Activity Report - 2011
Annual report by ANDRA, the French National Radioactive Waste Management Agency, regarding its activities in 2011.
Activity and Sustainable Development Report - 2010
Activity and Sustainable Development Report - 2010
Annual report produced by ANDRA, the French National Radioactive Waste Management Agency describing its activities in 2010.
ANDRA Newsletter #8
ANDRA Newsletter #8
Newsletter produced by ANDRA, the French National Radioactive Waste Management Agency.
ANDRA Newsletter #7
ANDRA Newsletter #7
Newsletter produced by ANDRA, the French National Radioactive Waste Management Agency.
ANDRA Newsletter #6
ANDRA Newsletter #6
Newsletter produced by ANDRA, the French National Radioactive Waste Management Agency.
ANDRA Newsletter #5
ANDRA Newsletter #5
Newsletter produced by ANDRA, the French National Radioactive Waste Management Agency.