The Experts below are selected from a list of 39069 Experts worldwide ranked by ideXlab platform
B. Peter Mcgrail - One of the best experts on this subject based on the ideXlab platform.
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SubSurface Transport Over Reactive Multiphases (STORM): A general, coupled, nonisothermal multiphase flow, reactive transport, and porous medium alteration simulator, Version 2 user's guide
2000Co-Authors: Diana H. Bacon, Mark D White, B. Peter McgrailAbstract:The Hanford Site, in southeastern Washington State, has been used extensively to produce nuclear materials for the US strategic defense arsenal by the Department of Energy (DOE) and its predecessors, the US Atomic Energy Commission and the US Energy Research and Development Administration. A large inventory of radioactive and mixed waste has accumulated in 177 buried single- and double shell tanks. Liquid waste recovered from the tanks will be pretreated to separate the low-activity fraction from the high-level and transuranic wastes. Vitrification is the leading option for immobilization of these wastes, expected to produce approximately 550,000 metric tons of Low Activity Waste (LAW) glass. This total tonnage, based on nominal Na{sub 2}O oxide loading of 20% by weight, is destined for disposal in a near-Surface Facility. Before disposal of the immobilized waste can proceed, the DOE must approve a performance assessment, a document that described the impacts, if any, of the disposal Facility on public health and environmental resources. Studies have shown that release rates of radionuclides from the glass waste form by reaction with water determine the impacts of the disposal action more than any other independent parameter. This report describes the latest accomplishments in the development of a computational tool, SubSurface Transport Over Reactive Multiphases (STORM), Version 2, a general, coupled non-isothermal multiphase flow and reactive transport simulator. The underlying mathematics in STORM describe the rate of change of the solute concentrations of pore water in a variably saturated, non-isothermal porous medium, and the alteration of waste forms, packaging materials, backfill, and host rocks.
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Source Term Analysis for Hanford Low-Activity Tank Waste using the Storm Code: A Coupled Unsaturated Flow and Reactive Transport Model
Science and Technology for Disposal of Radioactive Tank Wastes, 1998Co-Authors: Diana H. Bacon, B. Peter McgrailAbstract:Liquid waste recovered from the 177 underground storage tanks at the Hanford Site near Richland, Washington will be pretreated to separate the low-activity fraction from the high-level and transuranic wastes [Ecology 1996]. If vitrification is selected for immobilization of the low-activity wastes (LAW), then approximately 550,000 MT of LAW glass is expected to be produced and disposed at Hanford in a near-Surface Facility (Figure 1). The LAW at Hanford is among the largest volumes of waste within the U.S. Department of Energy (DOE) complex and is one of the largest inventories of long-lived radionuclides planned for disposal in a low-level waste Facility.
Diana H. Bacon - One of the best experts on this subject based on the ideXlab platform.
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SubSurface Transport Over Reactive Multiphases (STORM): A general, coupled, nonisothermal multiphase flow, reactive transport, and porous medium alteration simulator, Version 2 user's guide
2000Co-Authors: Diana H. Bacon, Mark D White, B. Peter McgrailAbstract:The Hanford Site, in southeastern Washington State, has been used extensively to produce nuclear materials for the US strategic defense arsenal by the Department of Energy (DOE) and its predecessors, the US Atomic Energy Commission and the US Energy Research and Development Administration. A large inventory of radioactive and mixed waste has accumulated in 177 buried single- and double shell tanks. Liquid waste recovered from the tanks will be pretreated to separate the low-activity fraction from the high-level and transuranic wastes. Vitrification is the leading option for immobilization of these wastes, expected to produce approximately 550,000 metric tons of Low Activity Waste (LAW) glass. This total tonnage, based on nominal Na{sub 2}O oxide loading of 20% by weight, is destined for disposal in a near-Surface Facility. Before disposal of the immobilized waste can proceed, the DOE must approve a performance assessment, a document that described the impacts, if any, of the disposal Facility on public health and environmental resources. Studies have shown that release rates of radionuclides from the glass waste form by reaction with water determine the impacts of the disposal action more than any other independent parameter. This report describes the latest accomplishments in the development of a computational tool, SubSurface Transport Over Reactive Multiphases (STORM), Version 2, a general, coupled non-isothermal multiphase flow and reactive transport simulator. The underlying mathematics in STORM describe the rate of change of the solute concentrations of pore water in a variably saturated, non-isothermal porous medium, and the alteration of waste forms, packaging materials, backfill, and host rocks.
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subSurface transport over reactive multiphases storm a general coupled nonisothermal multiphase flow reactive transport and porous medium alteration simulator version 2 user s guide
Other Information: Supercedes report DE00751979; PBD: 7 Mar 2000, 2000Co-Authors: Diana H. Bacon, Mark D White, Peter B McgrailAbstract:The Hanford Site, in southeastern Washington State, has been used extensively to produce nuclear materials for the US strategic defense arsenal by the Department of Energy (DOE) and its predecessors, the US Atomic Energy Commission and the US Energy Research and Development Administration. A large inventory of radioactive and mixed waste has accumulated in 177 buried single- and double shell tanks. Liquid waste recovered from the tanks will be pretreated to separate the low-activity fraction from the high-level and transuranic wastes. Vitrification is the leading option for immobilization of these wastes, expected to produce approximately 550,000 metric tons of Low Activity Waste (LAW) glass. This total tonnage, based on nominal Na{sub 2}O oxide loading of 20% by weight, is destined for disposal in a near-Surface Facility. Before disposal of the immobilized waste can proceed, the DOE must approve a performance assessment, a document that described the impacts, if any, of the disposal Facility on public health and environmental resources. Studies have shown that release rates of radionuclides from the glass waste form by reaction with water determine the impacts of the disposal action more than any other independent parameter. This report describes the latest accomplishments in the development of a computational tool, SubSurface Transport Over Reactive Multiphases (STORM), Version 2, a general, coupled non-isothermal multiphase flow and reactive transport simulator. The underlying mathematics in STORM describe the rate of change of the solute concentrations of pore water in a variably saturated, non-isothermal porous medium, and the alteration of waste forms, packaging materials, backfill, and host rocks.
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Source Term Analysis for Hanford Low-Activity Tank Waste using the Storm Code: A Coupled Unsaturated Flow and Reactive Transport Model
Science and Technology for Disposal of Radioactive Tank Wastes, 1998Co-Authors: Diana H. Bacon, B. Peter McgrailAbstract:Liquid waste recovered from the 177 underground storage tanks at the Hanford Site near Richland, Washington will be pretreated to separate the low-activity fraction from the high-level and transuranic wastes [Ecology 1996]. If vitrification is selected for immobilization of the low-activity wastes (LAW), then approximately 550,000 MT of LAW glass is expected to be produced and disposed at Hanford in a near-Surface Facility (Figure 1). The LAW at Hanford is among the largest volumes of waste within the U.S. Department of Energy (DOE) complex and is one of the largest inventories of long-lived radionuclides planned for disposal in a low-level waste Facility.
K. M. Olson - One of the best experts on this subject based on the ideXlab platform.
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Estimate of the source term for a repository Surface Facility from the routine processing of spent fuel
High Level Radioactive Waste Management, 1990Co-Authors: J. Mishima, K. M. OlsonAbstract:The potential for release of radioactive material from the proposed handling and processing of spent nuclear fuel in a Surface Facility for a geologic repository was evaluated. The potential sources evaluated were 1) the crud that can be spalled from the exterior Surfaces of the spent fuel and hardware, 2) the contained radionuclides that can be released from cladding failure, and 3) the Surface contamination that could be resuspended from the cell and equipment Surfaces. The radionuclides in particulate forms are assumed to pass through the emission control system.
James H. Clarke - One of the best experts on this subject based on the ideXlab platform.
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ESTIMATING THE FREQUENCIES OF DROP EVENTS DURING THE PRECLOSURE EMPLACEMENT PERIOD AT YUCCA MOUNTAIN, NEVADA
Nuclear Technology, 2010Co-Authors: L. Spradley, Mark Abkowitz, James H. ClarkeAbstract:This research estimates the likelihood of the number of occurrences of three internal events involving crane transfers during the potential 50-year preclosure operational period of Yucca Mountain (YM): (a) drop of a bare-fuel assembly, (b) drop of a transport, aging, and disposal canister, and (c) drop of a dual-purpose canister. The analysis employs a model developed by the authors for predicting the packaging and thermal characteristics of waste streams arriving at YMand is related to a study on throughput for the Surface facilities that was also conducted by the authors using the model. The model generates waste streams for commercial spent nuclear fuel as a function of repository design parameters and operating strategies. Waste streams arriving at the repository are assumed to be routed for processing in the Surface facilities based on the thermal properties of the packages. This allows for estimation of the number of material crane transfers associated with each waste stream. The number of drops over the preclosure period is described as a binomial distribution, where each crane transfer is treated as an identical, independent trial with an outcome of drop or no drop. Results indicate that the drop events are not expected to occur one or more times during the preclosure operational period. This paper demonstrates an approach for estimating the likely distributions for frequencies of drop events, accounting for uncertainty in waste stream quantities in addition to changing assumptions about the crane drop rate. While it is recognized that results of this analysis are specific to YM Surface Facility design, the approach can be adapted for similar systems designed for centralized interim storage.
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ESTIMATING Surface Facility THROUGHPUT DURING THE PRECLOSURE EMPLACEMENT PERIOD AT YUCCA MOUNTAIN
Nuclear Technology, 2010Co-Authors: L. Spradley, Mark Abkowitz, James H. ClarkeAbstract:This paper focuses on how variations in commercial spent nuclear fuel shipment schedules have the potential to impact preclosure operations at the proposed repository for high-level waste at Yucca Mountain (YM) in Nevada. The analysis employs a simulation tool developed by the authors for modeling the packaging and thermal characteristics of the waste stream arriving at Yucca Mountain and is related to a study on the safety of the Surface facilities that was also conducted by the authors using the simulation tool. The objective of the research is to gain a better understanding of how waste-stream variations affect Surface Facility throughput, defined as the rate at which packages are prepared for aging or emplacement in the Surface facilities at YM. The basis for and adequacy of the preliminary Surface Facility throughput requirements are reviewed by evaluating throughput performance subject to various preclosure operating scenarios. Results indicate that under most scenarios, the preliminary design adequately accommodates the mean demand over the operating lifetime for the canister receipt and closure Facility (CRCF) and receipt Facility (RF) but not the wet handling Facility (WHF). While results indicate that WHF demand is likely to be higher than capacity in many scenarios, it seems reasonable that dual-purpose cask and truck deliveries could be deferred to maintain WHF operations at near-capacity levels. Results also show a high potential for variability in annual throughput demand at the CRCF and RF that might result in system backups. In the event of bottlenecks, the Facility with less demand can fulfill functional roles of one that is overburdened. The overlap of functional capability in facilities incorporatesflexibility into the system. However, since throughput targets are named per Facility, as opposed to functions of the system, the design goals of the system as a whole are obscured. An alternative design is proposed that is based on functional goals within the facilities, along with other recommendations.
J. Mishima - One of the best experts on this subject based on the ideXlab platform.
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Estimate of the source term for a repository Surface Facility from the routine processing of spent fuel
High Level Radioactive Waste Management, 1990Co-Authors: J. Mishima, K. M. OlsonAbstract:The potential for release of radioactive material from the proposed handling and processing of spent nuclear fuel in a Surface Facility for a geologic repository was evaluated. The potential sources evaluated were 1) the crud that can be spalled from the exterior Surfaces of the spent fuel and hardware, 2) the contained radionuclides that can be released from cladding failure, and 3) the Surface contamination that could be resuspended from the cell and equipment Surfaces. The radionuclides in particulate forms are assumed to pass through the emission control system.
