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Diffusion Barrier Transport Properties of Unsaturated Paintbrush Tuff Rubble Backfill
Diffusion coefficients (D) were experimentally determined in unsaturated tuff gravel to evaluated the effectiveness of tuff gravel and rubble as a diffusion barrier to ionic transport...

A Waste Package Strategy for Regulatory Compliance
This paper summarizes the strategy given in the Site Characterization Plan (SCP) for demonstrating complicance with the post closure performance objectives for the waste package and the...

Container Material Selection, Modeling and Testing
Virtually all of the approximately 40,000 high-level nuclear wast containers to be emplaced at Yucca Mountain must remain intact for 1,000 years to satisfy Nuclear Regulatory Commission...

MIIT; International In-Situ Testing of Simulated HLW Forms?Preliminary Analyses of SRL 165/TDS Waste Glass and Metal Systems
The first in-situ tests involving burial of simulated high-level waste (HLW) forms conducted in the United States were started on July 22, 1986. This effort, called the Materials Interface...

TN28V High Capacity Cask for the Transport and Storage of Vitrified Wastes
When the option of reprocessing has been selected, closing of the fuel cycle implies the return shipment of reprocessing wastes back to the country of origin of the spent fuel, in particular...

A Numerical Study of Some Effects of Nuclear Fuel Waste Vault Construction and Closure on Evolution of Groundwater Flow Paths in the Geosphere
We have performed a series of three dimensional finite-element simulations on the sensitivity of the groundwater flow paths and travel times in a conceptual hydrogeological model with...

Dynamic Use of Geoscience Information to Develop Scientific Understanding for a Nuclear Waste Repository
The development and safety evaluation of a nuclear waste geologic repository require a proper scientific understanding of the site response. Such scientific understanding depends on information...

Infill Sampling Design for Geologic Site Characterization of Potential High-Level Radioactive Waste Repositories
Geologic site characterization is fundamental to the selection and design of a high-level radioactive waste repository. Yet, to date, the simple question 'how many samples...

Plans for Characterization of the Potential Geologic Repository Site at Yucca Mountain, Nevada
Site investigations in the vicinity of the potential repository site at Yucca Mountain, Nevada, have occurred for many years. This is due to the proximity of the potential repository site...

Surface-Based Site Characterization Testing to Determine the Suitability of the Yucca Mountain Site for a Nuclear Waste Repository
The Yucca Mountain Site in Nevada is currently being evaluated by the U.S. Department of Energy to determine its suitability for the first U.S. high-level radioactive waste repository....

Assessment of Natural Resources in Repository Siting
One way to discourage people from intruding into a repository for high-level radioactive waste is to locate it at a place that is not valuable for mineral resources. Thus, the Nuclear...

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...

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...

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...

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...

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...

 

 

 

 

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