TN28V High Capacity Cask for the Transport and Storage of Vitrified Wastes
When the option of reprocessing has been selected, closing of the fuel cycle implies the return shipment of reprocessing wastes back to the country of origin of the spent fuel, in particular...
The Analysis of Horizontal Cooling Enhancement for Nuclear Waste Container Emplacement
This paper presents a novel method for distributing the heat generated by waste containers emplaced in the proposed high-level nuclear waste site at Yucca Mountain, Nevada. The method...
Systems Models for Predicting Radioactive Waste
This paper illustrates how a model can be constructed to analyze the growth of accumulated spent Light-Water-Reactor fuel using a technique from systems theory which has proved to be capable...
Investigation of Burnup Credit Allowance in the Criticality Safety Evaluation of Spent Fuel Casks
The payloads of present generation spent fuel casks are constrained by a criticality design basis that assumes loading with unirradiated fuel. This presentation discusses work in progress...
DOE-EM/Producers Strategy for Wasteform and Process Startup Acceptance
The high-level waste (HLW) sites are working closely with the Department of Energy's Office of Environmental Restoration and Waste Management (DOE-EM) to ensure that the activities...
Vitrification of Defense High Level Radioactive Waste at Savannah River and Hanford
The Department of Energy (DOE) is in the process of implementing two major elements of the Defense High-Level Radioactive Waste Management Program at two of the DOE production sites, namely...
High Level Radioactive Waste Management at the Savannah River Site
This paper describes the High Level Radioactive Waste (HLW) generated at the Savannah River Site (SRS), outlines how it has been managed over the 35 years since site operations began,...
Programmatic Challenges and the Value of Testing on the West Valley Demonstration Project's Vitrification Facility Design
The primary objective of the West Valley Demonstration Project (WVDP) is the solidification of approximately 2.1 million liters (560 thousand gallons) of high-level waste (HLW) which resulted...
An Overview of the Vitrification of Defense High-Level Waste at the Hanford Site
Nearly 63 percent of the nation's high-level nuclear waste has accumulated at the U.S. Department of Energy's (DOE) Hanford Site in Washington State. This accumulation...
Diffusion Coefficients and Hydraulic Conductivity in Unsaturated Hanford Soils and Sediments
Two groundwater transport parameters of some Hanford formation materials, the hydraulic conductivity and the diffusion coefficient, were measured to aid in predicting contaminant migration....
Reconnaissance ? ??C and ??8O Data from Trench 14, Busted Butte, and Drill Hole G-4, Yucca Mountain, Nevada Test Site
Trench 14 was excavated to investigate the extent of Quaternary movement on the Bow Ridge fault, a north-south structure on the east side of Yucca Mountain. The trench exposes calcite...
Sellafield?From High Level Notoriety to Intermediate Acceptance
After a highly publicised accident at Sellafield, involving radioactive pollution, a period of continuous adverse media coverage eroded public confidence in the plant and its operators,...
Choosing AT-Reactor Spent Fuel Storage Technologies
Need for expansion of the spent fuel storage capability of reactor sites was first caused by delays in construction of reprocessing facilities, later by cessation of commercial reprocessing...
Optimizing the Spent Fuel Transportation Cask for Spent Fuel Age and Burnup: A Preliminary Analysis
The U.S. Department of Energy (DOE) has been assigned responsibility for managing the nation's spent nuclear fuel (SNF). Because of the large quantity of SNF to be moved,...
Vapor Hydration and Subsequent Leaching of Transuranic-Containing SRL and WV Glasses
High-level nuclear waste glass that is subject to disposal in the proposed unsaturated environment at Yucca Mountain, Nevada, initially will be altered through contact with humid air....
The Technical Review Group: An Application of the Quality Assurance Program Descriptions for Defense High-Level Waste Processing
This paper describes the formation of a technical review group (TRG) as an early application of the quality assurance program for high-level waste processing. The objectives and functions...
The DWPF Product, and Its Qualification Program
The Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS) will be the first facility in the nation capable of immobilizing high-level nuclear waste. Production of DWPF...
Estimate of the Source Term for a Repository Surface Facility From the Routine Processing of Spent Fuel
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...
Effect of Minor Actinide Removal From Fission Products Before Vitrification on the Radiological Impact of a High Level Waste Deep Repository
The topic of this work is to assess the effect of minor actinide (Cm, Am, Np) removal from fission products before vitrification on the radiological impact of a vitrified waste geological...
The Source Term for HLW Disposal in the European Communities' R&D Programme
During the last five years, the EC's research programme on radioactive waste has focused much of its investigation in the field of HLW management on the source term for geologic...
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