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Facility Interface Capability Assessment (FICA) Project
The U.S. Department of Energy-Office of Civilian Radioactive Waste Management (DOE-OCRWM) is sponsoring the Facility Interface Capability Assessment Project to determine current and potential...

Acceptance of Spent Fuel of Varying Characteristics
This paper is a preliminary overview of a study with the primary objective of establishing a set of acceptance selection criteria and corresponding spent fuel characteristics to be incorporated...

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...

Investigation of Burnup Credit Allowance in the Criticality Safety Evaluation of Spent Fuel Casks
The payloads of present generation spent fuel casks are constrained by a criticality design basis that assumes loading with unirradiated fuel. This presentation discusses work in progress...

DOE-EM/Producers Strategy for Wasteform and Process Startup Acceptance
The high-level waste (HLW) sites are working closely with the Department of Energy's Office of Environmental Restoration and Waste Management (DOE-EM) to ensure that the activities...

Vitrification of Defense High Level Radioactive Waste at Savannah River and Hanford
The Department of Energy (DOE) is in the process of implementing two major elements of the Defense High-Level Radioactive Waste Management Program at two of the DOE production sites, namely...

High Level Radioactive Waste Management at the Savannah River Site
This paper describes the High Level Radioactive Waste (HLW) generated at the Savannah River Site (SRS), outlines how it has been managed over the 35 years since site operations began,...

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...

Building of a Conceptual Model at the UE25-C Hole Complex
U.S. Geological Survey and Lawrence Berkeley Laboratory are attempting to construct a conceptual model of the UE25-c hole complex. An interdisciplinary approach is discussed where all...

Combined Analytical/Numerical Approaches to Solving Fluid Flow Problems in the Unsaturated Zone at Yucca Mountain
Various analytical and numerical approaches are presented for the study of unsaturated flow processes in the vicinity of the Yucca Mountain, Nevada, the proposed site of an underground...

Prototype Testing for the Yucca Mountain Project
The U.S. Department of Energy, through its Yucca Mountain Project Office (YMPO), has been conducting prototype activities in welded and non-welded tuff. These activities are in preparation...

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...

Concepts in Prototype Testing for In Situ Geomechanical Investigations at Yucca Mountain
Geomechanical investigations comprise a significant portion of the site characterization program to be conducted at Yucca Mountain, the site of a proposed repository for nuclear waste....

Prototype Heater Test of the Environment Around a Simulated Waste Package
This paper presents selected results obtained during the 301 day duration of the Prototype Engineered Barrier System Field Test (PEBSFT) performed in G-Tunnel within the Nevada Test Site....

Tomographic Geophysics for Better Subsurface Geologic Information
Geologic skepticism among engineers owes much of its origin to common ambigueties in geologic interpretations and the innate artistic aspects of geology and its related diciplines. Geophysical...

Application of Geophysical Methods for Fracture Characterization
One of the most crucial needs in the design and implementation of an underground waste isolation facility is a reliable method for the detection and characterization of fractures in zones...

The Application of Vertical Seismic Profiling and Cross-Hole Tomographic Imaging for Fracture Characterization at Yucca Mountain
In order to obtain the necessary characterization for the storage of nuclear waste, much higher resolution of the features likely to affect the transport of radionuclides will be required...

 

 

 

 

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