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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...

A Description and Status of the Yucca Mountain Project Repository Sealing Program
Yucca Mountain is being characterized to determine its suitability as a site for a high-level nuclear waste repository. The repository would be located in the unsaturated zone in fractured,...

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...

The Analysis of Horizontal Cooling Enhancement for Nuclear Waste Container Emplacement
This paper presents a novel method for distributing the heat generated by waste containers emplaced in the proposed high-level nuclear waste site at Yucca Mountain, Nevada. The method...

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...

Systems Models for Predicting Radioactive Waste
This paper illustrates how a model can be constructed to analyze the growth of accumulated spent Light-Water-Reactor fuel using a technique from systems theory which has proved to be capable...

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...

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...

 

 

 

 

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