Deep Borehole Field Test Site Characterization
Abstract not provided.
Publications
Draft Geologic Disposal Requirements Basis for STAD Specification
This document provides the basis for requirements in the current version of Performance Specification for Standardized Transportation, Aging, and Disposal Canister Systems, (FCRD-NFST-2014-0000579) that are driven by storage and geologic disposal considerations. Performance requirements for the Standardized Transportation, Aging, and Disposal (STAD) canister are given in Section 3.1 of that report. Here, the requirements are reviewed and the rationale for each provided. Note that, while FCRD-NFST-2014-0000579 provides performance specifications for other components of the STAD storage system (e.g. storage overpack, transfer and transportation casks, and others), these have no impact on the canister performance during disposal, and are not discussed here.
Cavern/Vault Disposal Concepts and Thermal Calculations for Direct Disposal of 37-PWR Size DPCs
This report provides two sets of calculations not presented in previous reports on the technical feasibility of spent nuclear fuel (SNF) disposal directly in dual-purpose canisters (DPCs): 1) thermal calculations for reference disposal concepts using larger 37-PWR size DPC-based waste packages, and 2) analysis and thermal calculations for underground vault-type storage and eventual disposal of DPCs. The reader is referred to the earlier reports (Hardin et al. 2011, 2012, 2013; Hardin and Voegele 2013) for contextual information on DPC direct disposal alternatives.
Handling and Emplacement Options for Deep Borehole Disposal Conceptual Design
Abstract not provided.
Investigations of Dual-Purpose Canister Direct Disposal Feasibility
Abstract not provided.
Nuclear Waste and Fuel Cycle Activities
Abstract not provided.
Siting Considerations for a Deep Borehole Disposal Facility - Slides
Abstract not provided.
Field-scale Thermal Testing in a Generic Salt Disposal Environment Underground Research Laboratory (URL): Delineation of Principal Purpose Objectives and Hypotheses
The amount of brine present in domal salt formation is far less than in bedded salts (e.g., 0.01 to 0.1% compared with 1 to 3%). In salt domes, shear deformation associated with diapirism has caused existing brine to coalesce, leading to flow and expulsion. Brine migration behavior was investigated in bedded salt at WIPP (Nowak and McTigue 1987, SAND87-0880), and in domal salt at Asse (Coyle et al. 1987, BMI/ONWI-624). Test methods were not standardized, and the tests involved large diameter boreholes (17 to 36 in. diameter) and large apparatus. The tested intervals were proximal to mined openings (within approximately 1 diameter) where in situ stresses are redistributed due to excavation. The tests showed that (1) brine inflow rates can range over at least 2 orders of magnitude for domal vs. bedded salt, (2) that brine inflow is strongly associated with clay and interbedded permeable layers in bedded salt, and (3) that measurement systems can readily collect very small quantities of moisture over time frames of 2 years or longer. Brine inflow rates declined slightly with time in both test series, but neither series approached a state of apparent depletion. This range of flow magnitude could be significant to repository design and performance assessment, especially if inflow rates can be predicted using stratigraphic and geomechanical inputs, and can be shown to approach zero in a predictable manner.
Site characterization for a deep borehole field test
15th International High-Level Radioactive Waste Management Conference 2015, IHLRWM 2015
Deep Borehole Disposal (DBD) of radioactive waste has some clear advantages over mined repositories, including incremental construction and loading, enhanced natural barriers provided by deep continental crystalline basement, and reduced site characterization. Unfavorable features for a DBD site include upward vertical fluid potential gradients, presence of economically exploitable natural resources, presence of high permeability connection from the waste disposal zone to the shallow subsurface, and significant probability of future volcanic activity. Site characterization activities would encompass geomechanical (i.e., rock stress state, fluid pressure, and faulting), geological (i.e., both overburden and bedrock lithology), hydrological (i.e., quantity of fluid, fluid convection properties, and solute transport mechanisms), chemical (i.e., rock and fluid interaction), and socioeconomic (i.e., likelihood for human intrusion) aspects. For a planned Deep Borehole Field Test (DBFT), site features and/or physical processes would be evaluated using both direct (i.e., sampling and in-hole testing) and indirect (i.e., surface and borehole geophysical) methods for efficient and effective characterization. Surface-based characterization would be used to guide the exploratory drilling program, once a candidate DBFT site has been selected. Borehole based characterization will be used to determine the variability of system state (i.e., stress, pressure, temperature, petrology, and water chemistry) with depth, and to develop material and system parameters relevant for numerical simulation. While the site design of DBD could involve an array of disposal boreholes, it may not be necessary to characterize each borehole in detail. Characterization strategies will be developed in the DBFT that establish disposal system safety sufficient for licensing a disposal array.
Research needs for deep boreholes
15th International High-Level Radioactive Waste Management Conference 2015, IHLRWM 2015
While deep borehole disposal of nuclear waste should rely primarily on off-the-shelf technologies pioneered by the oil and gas and geothermal industries, the development of new science and technology will remain important. Key knowledge gaps have been outlined in the research roadmap for deep boreholes (B. Arnold et al, 2012, Research, Development, and Demonstration Roadmap for Deep Borehole Disposal, Sandia National Laboratories, SAND2012-8527P) and in a recent Deep Borehole Science Needs Workshop. Characterizing deep crystalline basement, understanding the nature and role of deep fractures, more precisely age-dating deep groundwaters, and demonstrating long-term performance of seals are all important topics of interest. Overlapping deep borehole and enhanced geothermal technology needs include: quantification of seal material performance/failure, stress measurement beyond the borehole, advanced drilling and completion tools, and better subsurface sensors. A deep borehole demonstration has the potential to trigger more focused study of deep hydrology, high temperature brine-rock interaction, and thermomechanical behavior.
A case for direct disposal of SNF in existing DPCs
15th International High-Level Radioactive Waste Management Conference 2015, IHLRWM 2015
Commercial spent nuclear fuel (SNF) continues to accumulate in dry storage, sealed into welded dual-purpose canisters (DPCs). Direct disposal of DPCs, without cutting them open and re-packaging the fuel, is technically feasible at least for some DPCs and some disposal concepts. Options for DPC direct disposal are taking form, based on an ongoing study by the U.S. Department of Energy. Direct disposal of DPCs should be viewed as one part of a diverse fuel management system that will eventually switch to loading standardized multi-purpose canisters (MPCs). Nearly all DPCs that are loaded before this switch could be directly disposed depending on the disposal environment selected. DPC direct disposal options have been developed for salt, crystalline and sedimentary host media. These options are suited to different populations of DPCs, ranging from those containing older, colder fuel (e.g., in sedimentary media) to all DPCs (salt). The timing of DPC use offers an opportunity to simplify the SNF management system. Commercial SNF will be generated in the U.S. for more than 90 years, whereas facility lifetimes are typically on the order of 50 years. Efficiencies could be realized by implementing disposal in "campaigns. " Additional accumulation of DPCs over the next 10 to 20 years, followed by a transition to MPCs, would define two such campaigns. A repository could first be constructed for MPCs, and disposal of DPCs could be deferred and addressed later using new, dedicated facilities. During the interim storage period DPC thermal output would decay, further expanding disposal options.
Canister Design for Spent Fuel Disposal in a Range of Geologic Disposal Environments
Abstract not provided.
Disposal of Spent Nuclear Fuel in Dual-Purpose and Multi-Purpose Canisters
Abstract not provided.
Investigations of Dual-Purpose Canister Direct Disposal Feasibility ? 15106
Abstract not provided.
System-Level Logistics Modeling of DPC Direct Disposal
Abstract not provided.
A1 + A2: Overview of Radioactive Waste Management and Geologic Disposal R&D in the U.S
Abstract not provided.
A3 & A4: URLs in the U.S.: Planning Design Construction and Operation
Abstract not provided.
Deep Borehole Demonstration Project Overview
Abstract not provided.
A5 & A6: Repository Design and U.S. Examples
Abstract not provided.
A6a: Generic Disposal Concepts and Multi-Purpose Canister Strategies for Spent Nuclear Fuel
Abstract not provided.
Experimental plan for DPC/overpack performance in a repository
Abstract not provided.
DPC materials and corrosion environments
After an exposition of the materials used in DPCs and the factors controlling material corrosion in disposal environments, a survey is given of the corrosion rates, mechanisms, and products for commonly used stainless steels. Research needs are then identified for predicting stability of DPC materials in disposal environments. Stainless steel corrosion rates may be low enough to sustain DPC basket structural integrity for performance periods of as long as 10,000 years, especially in reducing conditions. Uncertainties include basket component design, disposal environment conditions, and the in-package chemical environment including any localized effects from radiolysis. Prospective disposal overpack materials exist for most disposal environments, including both corrosion allowance and corrosion resistant materials. Whereas the behavior of corrosion allowance materials is understood for a wide range of corrosion environments, demonstrating corrosion resistance could be more technically challenging and require environment-specific testing. A preliminary screening of the existing inventory of DPCs and other types of canisters is described, according to the type of closure, whether they can be readily transported, and what types of materials are used in basket construction.
Materials for Consideration in Standardized Canister Design Activities
This document identifies materials and material mitigation processes that might be used in new designs for standardized canisters for storage, transportation, and disposal of spent nuclear fuel. It also addresses potential corrosion issues with existing dual-purpose canisters (DPCs) that could be addressed in new canister designs. The major potential corrosion risk during storage is stress corrosion cracking of the weld regions on the 304 SS/316 SS canister shell due to deliquescence of chloride salts on the surface. Two approaches are proposed to alleviate this potential risk. First, the existing canister materials (304 and 316 SS) could be used, but the welds mitigated to relieve residual stresses and/or sensitization. Alternatively, more corrosion-resistant steels such as super-austenitic or duplex stainless steels, could be used. Experimental testing is needed to verify that these alternatives would successfully reduce the risk of stress corrosion cracking during fuel storage. For disposal in a geologic repository, the canister will be enclosed in a corrosion-resistant or corrosion-allowance overpack that will provide barrier capability and mechanical strength. The canister shell will no longer have a barrier function and its containment integrity can be ignored. The basket and neutron absorbers within the canister have the important role of limiting the possibility of post-closure criticality. The time period for corrosion is much longer in the post-closure period, and one major unanswered question is whether the basket materials will corrode slowly enough to maintain structural integrity for at least 10,000 years. Whereas there is extensive literature on stainless steels, this evaluation recommends testing of 304 and 316 SS, and more corrosion-resistant steels such as super-austenitic, duplex, and super-duplex stainless steels, at repository-relevant physical and chemical conditions. Both general and localized corrosion testing methods would be used to establish corrosion rates and component lifetimes. Finally, it is unlikely that the aluminum-based neutron absorber materials that are commonly used in existing DPCs would survive for 10,000 years in disposal environments, because the aluminum will act as a sacrificial anode for the steel. We recommend additional testing of borated and Gd-bearing stainless steels, to establish general and localized corrosion resistance in repository-relevant environmental conditions.
URL Cost and Design Considerations
Abstract not provided.
Technical Feasibility of Measuring Low-Stress Low Strain-Rate Deformation Relevant to a Salt Repository
Abstract not provided.
Results 126–150 of 211