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Analysis and Evaluation of Regulatory Uncertainties in 10 CFR 60 Subparts B and E
An attribute analysis scheme is presented for for prioritizing the resolution of regulatory uncertainties. Attributes are presented which assist in identifying the importance, need for...

Transportation Legend, Fact and Hysteria or, How to Dismantle a Mature Industry
In the rush to 'correct' the perceived deficiencies in the regulations covering the transportation of radioactive materials, many people, from legislators to...

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...

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...

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...

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...

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,...

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,...

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...

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...

The Use of Performance Assessments in Yucca Mountain Repository Waste Package Design Activities
The Yucca Mountain Project is developing performance assessment approaches as part of the evaluations of the suitability of Yucca Mountain as a repository site. Lawrence Livermore National...

Prediction of Long-Term Behavior of Waste Package Materials in a Geologic Repository
An ASTM Standard Practice is under development as a national consensus standard on how to make and validate predictions of the long-term behavior of waste package materials in a deep geologic...

Social Issues and Challenges in the Disposal of Nuclear Waste
Equity and the perception of fairness are issues equal in importance to technical validity in the development of high-level waste management programs. With the passage of the Nuclear Waste...

Incorporation of Reprocessing Raffinates and High Level Solids in Cement
Reprocessing highly enriched uranium fuel from UKAEA Materials Testing Reactors produces highly active aqueous raffinate. This is currently stored. The UK strategy is for raffinate immobilisation,...

 

 

 

 

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