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Optimization Method for Dimensioning a Geological HLW Waste Repository
This method was developed by the CEA to optimize the dimensions of a geological repository by taking account of technical and economic parameters. It involves optimizing radioactive waste...

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...

Evaluation of the Canadian HLW Disposal Program?Performance Assessment Aspects
The inception and development of the Canadian HLW disposal program are described, showing its basis in the multi-barrier system concept and noting the mechanisms in place for its evaluation...

Defining the Need for and Functions of the Monitored Retrievable Storage (MRS) Facility
A series of system studies of the Civilian Radioactive Waste Management System were conducted by the Department of Energy (DOE) to determine the role for a Monitored Retrievable Waste...

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...

A Demonstration of the Systems Integration Modeling System (SIMS) as a Decision-Support Tool
In April 1989, the Office of Civilian Radioactive Waste Management (OCRWM) Integration Branch completed major demonstration of the Systems Integration Modeling System (SIMS). That system...

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...

 

 

 

 

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