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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).
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).
An Historical and Prospective View of Romanian Decision Making in the Nuclear Domain
An Historical and Prospective View of Romanian Decision Making in the Nuclear Domain
The following graphics were developed by NF Marin Constantin (INR) for presentation and discussion at the 2nd NSG meeting in Romania (January 2008). 1. DMP for LILW Repository in Romania - Main Phases 2. Romanian History of Nuclear Power - Main Facts and Decisions 3. Cernavoda Area DMP: Dialogue Planning Including CIP Actions 4. Hypothetical Nuclear Industry Formulation of the DMP Stakes and Issues 5. Hypothetical Public Formulation of the DMP Stakes and Issues 6. How to Improve the Public Contribution to the DMP? Proposal for NSG Discussion
D1-9 Prospective Case Study - Romania
D1-9 Prospective Case Study - Romania
Impact of Nuclear Information on Young People's Knowledge and Attitudes: Methods/Participatory tools in an Educational Program WP1
Impact of Nuclear Information on Young People's Knowledge and Attitudes: Methods/Participatory tools in an Educational Program WP1
Despite in Romania nuclear research activities were started in early 50s, the nuclear power is very young. First NPP, Cernavoda Unit 1, about 600 MWe, was in operation since 1996. Next unit (Cernavoda Unit2) will be in operation at the end of 2007. Therefore, a relative low amount of high level waste was produced. However, some problems already exists in Romania, mainly related to historical radioactive wastes released by nuclear industry and research.