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Concrete Cask Storage Technology
The paper presents the design and operation of the new dry storage system for nuclear waste. The system was designed by complete nuclear, thermal-hydraulic and structural analysis to the...

Comparative Analyses of Spent Nuclear Fuel Transport Modal Options
The movement of nuclear waste can be accomplished by various transport modal options involving different types of vehicles, transport casks, transport routes, and intermediate intermodal...

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,...

Transportation Cask Life Cycle Cost Uncertainty Analysis
This paper demonstrates an uncertainty analysis methodology using random sampling. This methodology has been applied to a nuclear waste transportation code, and several transportation...

Size and Transportation Capabilities of the Existing U.S. Cask Fleet
This study investigates the current spent nuclear fuel cask fleet capability in the United States. In addition, it assesses the degree to which the current fleet would be available, as...

Analysis of RADTRAN Transportation Model
The RADTRAN computer model, used to estimate the risks of transporting waste to a high-level repository, is critically reviewed. Ignoring high consequence accidents, human error, sabotage,...

Accident Analyses in Fulfillment of the Requirements of the National Environmental Policy Act and Their Relationship to the Packaging and Testing Requirements of the Nuclear Regulatory Commission
In planning its Transportation Program, the Office of Civilian Radioactive Waste Management must address two fundamental questions: (1) To what extent are the reasonably foreseeable significant...

Properties of the West Valley Waste Form
The centroid composition of the West Valley Demonstration Project waste form has been selected on the basis of criteria mandating high chemical durability and good processibility. A review...

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....

Recent Results on the Effect of Gamma Radiation on the Durability and Microstructure of DWPF Glass
The effect of gamma radiation on the durability and microstructure of a simulated nuclear waste glass from the Savannah River Site has been carefully investigated. Three large pieces of...

Soluble High-Level Waste Decontamination and Disposal at the Savannah River Site
The high-level radioactive waste that has accumulated at the Savannah River Site is stored in large underground steel tanks. Programs to remove the soluble waste from the storage tanks,...

Volatilization of Cesium and Ruthenium From High-Level Waste Glass
The contamination of the air above high-level waste glass by ¹³⁴Cs, ¹³⁷Cs and ¹⁰⁶Ru...

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...

Assuring Quality Measurements of Environmental Radioactivity for a High Level Waste Repository
Federal agencies have ordered detailed quality assurance documentation in procedures used for measuring environmental radioactivity during the site characterization phase at the proposed...

Requirements for Controlling a Repository's Releases of Carbon-14 Dioxide; The High Costs and Negligible Benefits
A repository excavated within the unsaturated zone may release carbon(C)-14 dioxide in amounts that exceed limits imposed by the Environmental Protection Agency (EPA) and the Nuclear Regulatory...

Systems Integration During the Development of a Federal Waste Management System
Systems integration in the development of the Federal Waste Management System for spent nuclear fuel and high-level radioactive waste involves not only the activities traditional to development...

 

 

 

 

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