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At least 1,153 records · Page 64
All sourcesNASA NTRSDOE OSTI
DOE OSTI2017

Assessment of the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Facility Vault Concrete Data

This document provides a summary of the concrete performance data collected during vault fabrication and installation. The report includes the process by which quality data was collected during vault fabrication and installation, the inspection requirements, and a summary of resulting test data with the potential to impact vault system durability. This report also includes quantitative data collected on cured concrete samples poured for random concrete batches throughout the concrete component fabrication process. Quantitative data includes total porosity, bulk density, absorption, effective porosity, and gas-phase permeability. Chloride diffusivity data collected during the concrete mix selection process are also included for completeness. Data shows that the vault quality assurance program resulted in components received insignificant defects and damaged areas during the fabrication stage and during the vault installation stage. Data collected on the cured concrete samples show the gas-phase permeability and effective porosity are slightly higher than the data used to select the concrete mix designs.

99 GENERAL AND MISCELLANEOUS↗
DOE OSTI2018

Assessing the Geomechanical Response of CO 2 Disposal in Flood Basalt Reservoirs

In this work, we complete a multi-scale investigation of the physical processes governing geologic CO 2 sequestration in basalt reservoirs. This work integrates (i) laboratory measurements of relative permeability in a basalt fracture, (ii) theoretical modeling to understand how relative permeability uncertainty affects geomechanical performance attributes of basalt reservoirs, (iii) outcrop-scale simulation to identify the characteristics of vertical CO 2 flow in a basalt fracture network, and (iv) regional-scale assessment of permeability architecture in the Columbia River Basalt Group (CRBG). These individual studies are combined into a site-scale stochastic model of geologic CO 2 sequestration in the Columbia River Plateau, which shows how bulk and relative permeability variability affects geomechanical reservoir integrity and storage capacity of flood basalt reservoirs. This project resulted in a novel laboratory technique that combines X-ray CT and micro-PET scanning to calculate the relative permeability curves for a horizontal fracture in basalt. We also discovered that permeability on the Columbia River Plateau exhibits directionally-dependent spatial correlation, which our analysis suggests is a result of loading-induced subsidence. This analysis further discovered that permeability in the CRBG may increase at depth due to bending moment stresses. In the context of CO 2 sequestration, this result implies that storage capacity and injectivity may actually increase at depths beyond ~1 km. Our outcrop-scale investigation found that buoyant, free-phase CO 2 tends to accumulate at fracture intersections, which inhibits vertical flow over 10+ year timescales and may facilitate both physical and chemical trapping as fluid mobility decreases. At the site-scale, we find that in flood basalt reservoirs the spatial configuration of reservoir permeability exhibits substantial control on CO 2 injectivity. We utilized known borehole geology from the Wallula Basalt Sequestration Pilot Project to develop 50 equally probable permeability configurations and found that a single injection well operating at 95% of the borehole breakout pressure can deliver 0.12 to 2.0 million metric tons of CO 2 per year (MMT CO 2 per year). This maximum injection rate can support a 1,000 MW gas-fired power plant with a single injection well.

58 GEOSCIENCES↗
DOE OSTI2019

Annual Status Report (FY 2018): Composite Analysis for Low Level Waste Disposal in the Central Plateau of the Hanford Site

In accordance with U.S. Department of Energy (DOE) requirements in DOE M 435.1-1 Chg 11, and as implemented by DOE/RL-2000-292, the DOE Richland Operations Office has prepared this annual summary of the Hanford Site Composite Analysis for fiscal year (FY) 2018. The Hanford Site Composite Analysis was originally reported in PNNL-118003 and PNNL-11800, Addendum 14 (hereinafter referred to collectively as the Hanford Site Composite Analysis). The Hanford Site Composite Analysis was approved by a 2002 memorandum. As required by DOE/RL-2000-29, an annual evaluation of new information and data developed by a number of onsite programs was completed. The reporting period for this annual evaluation is FY 2018 (October 1, 2017, through September 30, 2018).

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2019

Direct Disposal of Dual Purpose Canisters – LANL – Boral Solubility (FY19)

Three baseline hydrothermal experiments were conducted with deionized water and Neutron Absorber Composite, a commercially product manufactured by 3M TM (referred to by its former title, Boral®, in this report). Boral® is composed of boron carbide (B 4 C) sintered with Al and encased with aluminum cladding. Hydrothermal experiments were conducted 150, 230, and 300 °C and 150 bar for two weeks. Changes in the physical properties and mineralogy of the Boral® coupons were characterized with X-ray diffraction and scanning electron microscopy. Compositions of reaction fluids were monitored during and after each experiment. Results indicate that alteration of aluminum cladding to boehmite (AlO(OH)) occurs over the range of investigated temperatures but is most significant at 300 °C. The formation of boehmite is accompanied with H 2 gas. The crystal structure of boron carbide (B 4 C) appears to be unaltered by hydrothermal treatment; however aqueous boron was present in the reaction fluids.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2019

International Collaborations on Radioactive Waste Disposal in Salt

This report is a summary of the international collaboration and laboratory work funded by the US Department of Energy Office (DOE) of Nuclear Energy Spent Fuel and Waste Science & Technology (SFWST) as part of the Sandia National Laboratories Salt R&D work package. This report satisfies milestone level-four milestone M4SF-19SNO10303064. Several stand-alone sections make up this summary report, each completed by the participants. The first two sections discuss international collaborations on geomechanical benchmarking exercises (WEIMOS), granular salt reconsolidation (KOMPASS), engineered barriers (RANGERS), and documentation of Features, Events, and Processes (FEPs).

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DOE OSTI2018

Disposal Flowback Water Switch

This unit process acts as a switch to send flowback water waste from shale and tight natural gas well types to the appropriate water treatment plant options. To access the model referenced in the report, please visit https://www.netl.doe.gov/energy-analysis/details?id=9FF8585C-4753-429A-A508-8FCB1D53F2E7

03 NATURAL GAS↗
DOE OSTI2018

Disposal Produced Water Switch

This unit process acts as a switch to send produced water waste from all natural gas well types to the appropriate water treatment plant options. To access the model referenced in the report, please visit https://www.netl.doe.gov/energy-analysis/details?id=FFC018D0-653C-426C-A39F-A3411434B101

03 NATURAL GAS↗
DOE OSTI2019

Quantifying Holocene Cliff Retreat Rates at Technical Area 54, a Low- and Mixed-Level Radioactive Waste Disposal Site, Los Alamos National Laboratory, Los Alamos, New Mexico [Slides]

Cliff failure is occurring and threatens to expose pits and shafts. Steep slope angles = FoS < 1 = high probability of failure and retreat. EQ magnitude > 5.5 could initiate failure where FoS > 1. Fracture characterization (location, orientation, etc.) is essential for predictive analysis of at-risk cliff failure locations. Additional surface exposure dating would be helpful and further constrain the effect of fracture characteristics. Continued monitoring is essential for change detection and identification of areas with higher cliff retreat rates.

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DOE OSTI2019

Performance Metric for Cementitious Waste Form Inventory Release in the Integrated Disposal Facility

This report describes work supporting Phase 1 of the 2018 Department of Energy (DOE) Office of River Protection’s (ORP) Grand Challenge recipient proposal “Cementitious Immobilization of Treated LAW and Ancillary Benefits to Risk Reduction in Cross Site Transfer”. Phase 1 was to establish a performance metric for grout leachability against which laboratory leach data (as observed diffusivities) can be assed, followed by a comparison of historical test data against this metric. Historically, advancements in the cementitious (grout) waste form performance have been made over the last 40 years, with the majority of progress achieved within the past 8 years as part of the Washington River Protection Solutions, LLC testing program. This report presents a summary of that effort relevant to the Hanford Site.

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DOE OSTI2020

Composite Analysis for Low Level Waste Disposal in the Central Plateau of the Hanford Site (FY2019 Annual Status Report)

In accordance with DOE M 435.1-1 requirements and as implemented by DOE/RL-2000-29, the U.S. Department of Energy (DOE), Richland Operations Office has prepared this annual summary for fiscal year (FY) 2019. Originally reported in PNNL-11800 and PNNL-11800, Addendum 1, the Hanford Site Composite Analysis was approved through issuance of a 2002 memorandum. As required by DOE/RL-2000-29, an annual evaluation of new information and data developed by a number of onsite programs was completed. The reporting period for this annual evaluation is FY 2019 (October 1, 2018, through September 30, 2019). The information provided in this evaluation includes activities performed in FY 2019 that are considered pertinent to the Hanford Site Composite Analysis - information that could change source terms considered, and monitoring, research, and development results.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2020

International Collaborations on Radioactive Waste Disposal in Salt (FY20)

This report is a summary of the international collaboration work conducted by Sandia and funded by the US Department of Energy Office (DOE) of Nuclear Energy Spent Fuel and Waste Science & Technology (SFWST) as part of the Sandia National Laboratories Salt R&D and Salt International work packages. This report satisfies milestone level-three milestone M3SF-205N010303062. Several stand-alone sections make up this summary report, each completed by the participants. The first two sections discuss international collaborations on geomechanical benchmarking exercises (WEIMOS), granular salt reconsolidation (KOMPASS), engineered barriers (RANGERS), and documentation of Features, Events, and Processes (FEPs).

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DOE OSTI2020

M4SF-20LL010301082-Sorption Database and Model for Generic Disposal System Assessment

This progress report (Level 4 Milestone Number M4SF-20LL010301082) summarizes research conducted at Lawrence Livermore National Laboratory (LLNL) within the Argillite International Collaborations Activity Number Activity SF-20LL010301081. The activity is focused on our long-term commitment to engaging our partners in international nuclear waste repository research. The focus of this milestone is surface complexation model international collaborations. Specifically, we are developing a database framework for Spent Fuel and Waste and Science Technology (SFWST) that is aligned with the Helmholtz Zentrum Dresden Rossendorf (HZDR) sorption database development group in support of the database needs of the SFWST program.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2020

M4SF-20LL010301042: Updated Thermodynamic Database for Use in Generic Disposal System Assessment

This progress report (Level 4 Milestone Number M4SF-20LL010301042) summarizes research conducted at Lawrence Livermore National Laboratory (LLNL) within the Argillite Activity Number SF-20LL010301041. LLNL is leading efforts in the development of thermodynamic databases in support of the Spent Fuel and Waste Science Technology (SFWST) program. Thermodynamic models provide the basis for understanding the stability of solid phases and speciation of aqueous species and modeling the evolution of repository conditions. The LLNL effort is being performed in coordination with other US database development efforts. The effort includes a review of available thermochemical databases and a path forward for database integration. International coordination with the NEA-TDB is supported through crystalline international work package.

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