Social Impact Assessment of Siting the High-Level Nuclear Waste Repository in Nevada: The Use of Risk Future Scenarios in Survey Research
The proposed siting of a high-level nuclear waste repository in the State of Nevada has raised difficult problems with respect to assessing future social impacts. The projection of impacts...
The Development of Small Area Socioeconomic Data to be Utilized for Impact Analysis: Rural Southern Nevada
This paper describes the process by which economic and demographic estimates and projections will be prepared to determine the potential economic and demographic impacts that may result...
Beyond NEPA: A Look at Socioeconomic Impact Assessments Required Under the Nuclear Waste Policy Act, as Amended
The Department of Energy's Office of Civilian Radioactive Waste Management (OCRWM) has been charged by Congress, through the Nuclear Waste Policy Act, as amended (the Act),...
Spent Fuel and High-Level Waste Management in Selected Countries: Trends and Issues
This paper contains descriptions of the major parameters and plans for management of spent nuclear fuel and high-level radioactive wastes in Belgium, Canada, France, the Federal Republic...
Spent Fuel Storage Requirements for Nuclear Utilities and OCRWM
Projected spent fuel generation at U.S. power reactors exceeds estimated aggregate pool storage capacity by approximately 30,000 metric tons of uranium (MTU). Based on the current repository...
Site Selection Criteria for Constructing an Independent Spent Fuel Storage Installation (ISFSI) at a Commercial Nuclear Power Plant
Commercial nuclear power plants in the U.S. are responsible for providing their own interim storage for excess spent fuel. A facility located onsite, acting as a buffer between in-pool...
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...
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,...
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...
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...
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...
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...
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...
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