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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...

Important Factors in Developing a Nuclear Waste Management System
The nuclear waste management system provides unique challenges for a large and diverse segment of our society. For the politician there is the blending of national policy and the interests...

Probable Maximum Floods at the Yucca Mountain Exploratory Shafts
This paper presents an analysis of flood flows in the Coyote Wash at the proposed high level nuclear waste repository site at Yucca Mountain, Nevada. Estimates of the hydrographs at various...

Computed Distributions of Residual Shaft Drilling and Drift Construction Water in the Exploratory Facilities at Yucca Mountain, Nevada
The Yucca Mountain Project is studying the feasibility of constructing a high-level nuclear waste repository at Yucca Mountain in southwest Nevada. One activity of site characterization...

Hydrologic Characterization of Faults and Other Potentially Conductive Geologic Features in the Unsaturated Zone
The capability of characterizing near-vertical faults and other potentially highly conductive geologic features in the vicinity of a high-level-waste repository is of great importance...

Multi-Dimensional Modeling of Unsaturated Flow in the Vicinity of Exploratory Shafts and Fault Zones at Yucca Mountain, Nevada
Modeling studies were conducted to determine the potential effects of exploratory shafts on moisture distribution in the vicinity of an exploratory shaft facility, and the potential for...

Research for Final Disposal of Unreprocessed Spent Nuclear Fuel in Sweden
The second Swedish programme on research, development and demonstration in the nuclear radioactive waste management area was submitted by SKB to the Swedish National Board for Spent Nuclear...

Status of Site Investigations for Spent Fuel Repository in Finland
TVO's site programme aims at selection of a repository site for spent fuel by the end of 2000. A repository is planned to be constructed in the 2010's and commissioned...

Study of an Alternativefor Repository of Radioactive Waste?Taiwan Case
The accumlation of spent fuel and radioactive waste is forcing producers to look for repository systems in Taiwan. Tectonic setting, and geologic processes indicate that the Penghu Islands...

 

 

 

 

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