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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.
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Salt Repository Synthesis Data of Non-Delaware Basin and International Programs for the Storage/Disposal of Nuclear Waste
This report was developed in accordance with the LANL-Carlsbad Operations quality assurance program, specifically procedure LCO-QP6-1, Controlled Document Development, Change and Revision (LANL-CO, 2012). This deliverable is part of the scope developed for a salt research and development study completed on March 23, 2012 and agreed upon by the U.S. Department of Energy Offices of Nuclear Energy and Environmental Management.
Investigations on Repository Near-Field Thermal Modeling
Abstract not provided.
White Paper on Data Repository Reorganization Proposal for the xLPR Project
As the xLPR project moves along, it is important to properly manage the knowledge generated by the different groups. We focus specifically on the knowledge and communications written in files, including general documents, source code and executable files. Data generated through the project are different in nature and, for this reason, need to be treated differently. To that end, ORNL put in place a series of tools that facilitate proper storage and management of project data, document and code changes, group collaboration, knowledge transfer, transparency, accountability and auditability. This paper describes the approaches/tools that we recommend for moving the project forward on knowledge management.
Bentonite Evolution Under Experimental Repository Conditions [Slides]
Abstract Not Provided
Repository Layout and Required Ventilation Trade Studies in Clay/Shale using the DSEF Thermal Analytical Model
Abstract not provided.
Evaluation of Compatabilities Between the Test Program and a Potential Waste Repositories, or Other Users, at NTS
Abstract not provided.
Model Evaluation of the Thermo-Hydrological Response in Argillaceous Sedimentary Rock Repository for Direct Disposal of Dual-Purpose Canisters
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Review of underground construction methods and opening stability for repositories in clay/shale media
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Experimental plan for DPC/overpack performance in a repository.
Abstract not provided.
Technical Feasibility of Measuring Low-Stress Low Strain-Rate Deformation Relevant to a Salt Repository.
Abstract not provided.
Framework for Underground Research for Generic Repository Investigations in Salt
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Review of Underground Construction Methods and Opening Stability for Repositories in Clay/Shale Media
This report reviews the art and practice of excavating and constructing underground facilities in clay/shale media, as part of a multi-year evaluation of the technical feasibility of direct disposal of spent nuclear fuel (SNF) in dual-purpose canisters (DPCs). The purpose is to review worldwide examples of large-scale excavations in clay/shale media, the methods used for excavation and constructi on, and the costs. It is anticipated that this information will help to show the feasibility of construction for a deep geologic respository for (on the order of) 10,000 large, heavy, heat-generating waste packages. This report will refine the clay/shale disposal concept for DPC -based waste packages, in support of future studies that include cost estimation.
Modeling Radionuclide Transport in Fractured Rock for Next Generation Nuclear Waste Repository Performance Assessments [Slides]
Abstract not provided.
Thermal Performance Analysis of a Geologic Borehole Repository
The Brazilian Nuclear Research Institute (IPEN) proposed a design for the disposal of Disused Sealed Radioactive Sources (DSRS) based on the IAEA Borehole Disposal of Sealed Radioactive Sources (BOSS) design that would allow the entirety of Brazil’s inventory of DSRS to be disposed in a single borehole. The proposed IPEN design allows for 170 waste packages (WPs) containing DSRS (such as Co-60 and Cs-137) to be stacked on top of each other inside the borehole. The primary objective of this work was to evaluate the thermal performance of a conservative approach to the IPEN proposal with the equivalent of two WPs and two different inside configurations using Co-60 as the radioactive heat source. The current WP configuration (heterogeneous) for the IPEN proposal has 60% of the WP volume being occupied by a nuclear radioactive heat source and the remaining 40% as vacant space. The second configuration (homogeneous) considered for this project was a homogeneous case where 100% of the WP volume was occupied by a nuclear radioactive heat source. The computational models for the thermal analyses of the WP configurations with the Co-60 heat source considered three different cooling mechanisms (conduction, radiation, and convection) and the effect of mesh size on the results from the thermal analysis. The results of the analyses yielded maximum temperatures inside the WPs for both of the WP configurations and various mesh sizes. The heterogeneous WP considered the cooling mechanisms of conduction, convection, and radiation. The temperature results from the heterogeneous WP analysis suggest that the model is cooled predominantly by conduction with effect of radiation and natural convection on cooling being negligible. From the thermal analysis comparing the two WP configurations, the results suggest that either WP configuration could be used for the design. The mesh sensitivity results verify the meshes used, and results obtained from the thermal analyses were close to being independent of mesh size. The results from the computational case and analytically-calculated case for the homogeneous WP in benchmarking were almost identical, which indicates that the computational approach used here was successfully verified by the analytical solution.
Parameter Uncertainty for Repository Thermal Analysis
This report is one follow-on to a study of reference geologic disposal design concepts (Hardin et al. 2011a). Based on an analysis of maximum temperatures, that study concluded that certain disposal concepts would require extended decay storage prior to emplacement, or the use of small waste packages, or both. The study used nominal values for thermal properties of host geologic media and engineered materials, demonstrating the need for uncertainty analysis to support the conclusions. This report is a first step that identifies the input parameters of the maximum temperature calculation, surveys published data on measured values, uses an analytical approach to determine which parameters are most important, and performs an example sensitivity analysis. Using results from this first step, temperature calculations planned for FY12 can focus on only the important parameters, and can use the uncertainty ranges reported here. The survey of published information on thermal properties of geologic media and engineered materials, is intended to be sufficient for use in generic calculations to evaluate the feasibility of reference disposal concepts. A full compendium of literature data is beyond the scope of this report. The term “uncertainty” is used here to represent both measurement uncertainty and spatial variability, or variability across host geologic units. For the most important parameters (e.g., buffer thermal conductivity) the extent of literature data surveyed samples these different forms of uncertainty and variability. Finally, this report is intended to be one chapter or section of a larger FY12 deliverable summarizing all the work on design concepts and thermal load management for geologic disposal (M3FT-12SN0804032, due 15Aug2012).
Experiments and Modeling in Support of Generic Salt Repository Science
Salt is an attractive material for the disposition of heat generating nuclear waste (HGNW) because of its self-sealing, viscoplastic, and reconsolidation properties (Hansen and Leigh, 2012). The rate at which salt consolidates and the properties of the consolidated salt depend on the composition of the salt, including its content in accessory minerals and moisture, and the temperature under which consolidation occurs. Physicochemical processes, such as mineral hydration/dehydration salt dissolution and precipitation play a significant role in defining the rate of salt structure changes. Understanding the behavior of these complex processes is paramount when considering safe design for disposal of heat-generating nuclear waste (HGNW) in salt formations, so experimentation and modeling is underway to characterize these processes. This report presents experiments and simulations in support of the DOE-NE Used Fuel Disposition Campaign (UFDC) for development of drift-scale, in-situ field testing of HGNW in salt formations.