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What Will be the Engineered Barriers for Deep Disposal of High Level Radioactive Wastes in the Future?
Two sealing approaches are currently being developed in France for deep geological disposal of high-level wastes. One is based on the use of swelling clay in order to restore the initial...

Simulation Modeling of Subsurface Development
This paper discusses the use of simulation modeling in analyzing subsurface development activities and estimating associated costs at the Yucca Mountain candidate repository site. Described...

Development of the Engineered Barriers for the Deep Geological Disposal of High-Level Radioactive Waste
Vitrified waste, overpack and buffer material are under research and development as engineered barriers in the deep geological disposal system of high-level radioactive waste. Static leach...

Near-Field Modelling for the Safety Assessment of French High-Level Waste Repositories
In assessing the safety of a French high-level waste repository, the fluxes of radionuclides released by the near-field into the geosphere are modelled by the CONDIMENT source code. This...

Risk Perspective on Potential Releases of ?⁴C From the Geologic Repository at Yucca Mountain
The objective of this paper is to provide a perspective on the individual and population risks from potential releases of ¹⁴C from a geologic repository...

Deposition of Airborne Particles from Fractured Spent Fuel or High-Level Waste
Preliminary equations are developed to predict the amount of deposition of airborne particles that may result from an accidental release in a hot cell. The fraction of these airborne particles...

Trends in Waste Management Program Costs: An Evolution of Estimating Methods and Results
The purpose of this paper is to present a summary of how the program cost projections contained in the five TSLCC analyses performed to-date and the estimating methods used to make these...

Materials Selection Issues for Structural Components of Transportation Casks
Sandia National Laboratories (SNL) is evaluating the use of alternate materials (i.e. other than stainless steel) as structural components in nuclear spent fuel transportation casks. This...

Experience with Certifying Borated Stainless Steel as a Shipping Cask Basket Material
The original cask designs for a cask demonstration project featured fuel baskets constructed of borated stainless steel (bss) as a structural material. The project is intended to demonstrate...

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...

The International Stripa Project: Technology Transfer From Cooperation in Scientific and Technological Research on Nuclear Waste Disposal
The Nuclear Energy Agency of the Organization for Economic Cooperation and Development (OECD/NEA) sponsors the International Stripa Project. The Stripa Project is open to participation...

The Status of the Site Characterization and Validation Program in Phase III of the OECD/NEA Stripa Project
In 1980, the International Stripa Project was organized under the aegis of the OECD Nuclear Energy Agency for the purpose of conducting research, at the Stripa mine in Sweden, related...

The Role of Sensor Directed, Model-Based Control in Robotic Handling of Nuclear Waste Casks and Materials
This paper discusses the results from several projects at Sandia National Laboratories investigating the application of intelligent machine technologies to remote handling of nuclear waste...

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,...

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...

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,...

 

 

 

 

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