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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).
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.
Possible Strategies for Geoscientific Classification for High-Level Waste Repository Site Selection
Possible Strategies for Geoscientific Classification for High-Level Waste Repository Site Selection
This work was performed to suggest possible strategies for geoscientific classifications in the siting process of a high-level repository. To develop a feasible method for geoscientific classifications, a number of factors of a philosophical character, related to the purpose of the classifications, need to be accounted for. Many different approaches can be visualized, and this report was not intended to present a complete classification methodology.
Geological Disposal of Higher Activity Radioactive Wastes
Geological Disposal of Higher Activity Radioactive Wastes
This is one of three CoRWM reports to Government in 2009. The reports are about: <br><br>_ interim storage of higher activity wastes (including waste conditioning, packaging and transport, and the management of materials that may be declared to be wastes) <br>_ the implementation of geological disposal of higher activity wastes (this report) <br>_ research and development for interim storage and geological disposal. <br><br>The reports cover the three strands of the Government_s Managing Radioactive Waste Safely programme.
Managing our Radioactive Waste Safely: CoRWM's recommendations to Government
Managing our Radioactive Waste Safely: CoRWM's recommendations to Government
The Committee on Radioactive Waste Management was asked by Government in 2003 to make recommendations for the long-term management of the UK’s higher activity wastes that would both protect the public and the environment, and inspire public confidence. To do this, we have combined a technical assessment of options with ethical considerations, examination of overseas experience and a wide-ranging programme of engagement both with the public and with interested parties (stakeholders). I am happy to present our recommendations in the pages that follow.
Committee on Radioactive Waste Management Seventh Annual Report
Committee on Radioactive Waste Management Seventh Annual Report
This is the seventh CoRWM Annual Report. It summarises the outcomes of CoRWM’s scrutiny and advice work during the year. It also contains the Committee’s views on the current status of arrangements and plans for the long-term management of higher activity radioactive wastes in the UK. All the Committee Members have contributed to this Report and I am grateful to Marion Hill and the Secretariat for all their hard work in compiling it.
Committee on Radioactive Waste Management Eighth Annual Report
Committee on Radioactive Waste Management Eighth Annual Report
This is the eighth CoRWM Annual Report. It summarises CoRWM’s scrutiny and advice for the financial year ending on 31 March 2012. It also contains the Committee’s views on the status of arrangements and plans for the long-term management of higher activity radioactive wastes in the UK at June 2012.
ASSESSMENT OF THE GENERIC DISPOSAL SYSTEM SAFETY CASE for Information
ASSESSMENT OF THE GENERIC DISPOSAL SYSTEM SAFETY CASE for Information
The Committee on Radioactive Waste Management (CoRWM) has carried out an assessment of the generic Disposal System Safety Case (gDSSC) published by the Radioactive Waste Management Directorate (RWMD) of the Nuclear Decommissioning Authority (NDA) in February 2011. The assessment covered the whole suite of gDSSC documents, and related RWMD reports on research and development (R&D) and site characterisation.
Additional Media Studies for Site Suitability Criteria
Additional Media Studies for Site Suitability Criteria
Site suitability studies at LLL to date have considered repositories in bedded salt and shale.
NRC Comments on DOE Draft Environmental Assessment for the Deaf Smith County Site
NRC Comments on DOE Draft Environmental Assessment for the Deaf Smith County Site
Nuclear-Waste Disposal in Geologic Repositories
Nuclear-Waste Disposal in Geologic Repositories
Deep geologic repositories are being widely studied as the most favored method of disposal of nuclear waste. Scientists search for repository sites in salt, basalt, tuff and granite that are geologically and hydrologically suitable. The systematic evaluation of the safety and reliability of deep geologic disposal centers around the concept of interacting multiple barriers. The simplest element to describe of the geologic barrier is the physical isolation of the waste in a remote region at some depth within the rock unit.
U.S. DEPARTMENT OF ENERGY’S SITING GUIDELINES AT 10 CFR 963
U.S. DEPARTMENT OF ENERGY’S SITING GUIDELINES AT 10 CFR 963
The U.S. Department of Energy (DOE) has amended the policies under the Nuclear Waste Policy Act of 1982 for evaluating the suitability of Yucca Mountain, Nevada, as a site for development of a nuclear waste repository. The final rule at Title 10, Part 963 of the Code of Federal Regulations (10 CFR Part 963) focuses on the criteria and methodology to be used for evaluating relevant geological and other related aspects of the Yucca Mountain site.
Geological Challenges in Radioactive Waste Isolation
Geological Challenges in Radioactive Waste Isolation
Over the past forty years, the development of the technology needed to isolate radioactive waste in underground rock systems has been found to be a formidable problem. This is especially the case in connection with high-level waste (HLW) after its removal from operations in nuclear power plants. There is also the additional problem of isolating low- and intermediate-level waste (LILW).
Measures of Geologic Isolation
Measures of Geologic Isolation
Isolation in a geologic setting has been the generally favored solution to the high-level radioactive waste (HLW) problem since a scientific basis for nuclear waste management began to be formulated over half a century ago. Although general features of suitable settings have been enumerated, quantitative measures of the safety of geologic isolation of HLW are challenging to devise and to implement.
Review of the U.S. Department of Energy's National Survey of Crystalline Rocks
Review of the U.S. Department of Energy's National Survey of Crystalline Rocks
Location Performance Objectives for the NNWSI Area-to-Location Screening Activity
Location Performance Objectives for the NNWSI Area-to-Location Screening Activity
Fifty-four objectives were identified to guide the screening of the Nevada Research and Development Area of the Nevada Test Site for relatively favorable locations for the disposal of nuclear waste in a mined geologic repository. The objectives were organized as a hierarchy composed of 4 upper-level, 12 middle-level, and 38 lower-level objectives. The four upper-level objectives account for broad national goals to contain and isolate nuclear waste in an environmentally sound and economically acceptable manner.