A Proposed Methodology for Validating Performance Assessment Models for the DOE Office of Civilian Radioactive Waste Management Program
The Department of Energy (DOE) has developed a draft methodology for validating performance assessment models that will be used in the licensing of high-level waste repository systems....
Initiating Event Identification and Screening for Nuclear Waste Repository Preclosure Risk Assessment
This paper describes a method to identify potential initiating events that might occur during the preclosure phase at a nuclear waste repository proposed for the Yucca Mountain area of...
Preclosure Safety Analysis for a Prospective Yucca Mountain Conceptual Design Repository
A preliminary probabilistic risk assessment was performed for the prospective Yucca Mountain conceptual design repository. A new methodology to quantify radioactive source terms was developed...
Status of Integrated Performance Assessment of the Waste Packages and Engineered Barrier System
Performance assessment of the engineered barrier system for a nuclear waste repository combines information from relevant disciplines and predicts the net long-term performance of the...
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...
Role of Waste Packages in the Safety of a High Level Waste Repository in a Deep Geological Formation
The safety of a radioactive waste disposal facility lays on the three following barriers placed between the radioactive materials and the biosphere: the waste package, the engineered barriers,...
Optimizing Spent Fuel Cask Designs for Use in the Federal Waste Management System
The DOE will design and develop a new fleet of casks to transport spent fuel using innovative approaches to optimize the cask design. Preliminary casks designs indicate capacity increases...
State of Nevada Nuclear Waste Shipping Cask Design Studies
The State of Nevada has sponsored several contractor studies regarding nuclear waste shipping cask design issues. A comprehensive transportation needs assessment completed in 1988 recommended...
BR-100 Spent Fuel Shipping Cask Development
Continued public acceptance of commercial nuclear power is contingent to a large degree on the U.S. Department of Energy (DOE) establishing an integrated waste management system for spent...
An Innovative Cask for Transporting Defense High-Level Waste
In the early 1980s, the U.S. Department of Energy/Defense Programs (DOE/DP) initiated a project to develop a safe and efficient transportation system for defense high-level waste (DHLW)....
Social Realities in High-Level Radioactive Waste Management and Their Policy Implication
The management of high-level radioactive waste involves a number of enduring social realities that have posed major obstables to timely progress. These realities include: the deep-seated...
Current Social Systems Issues in the U.S. High Level Waste Management Program
Major changes in the U.S. high level waste management program since passage of the Nuclear Waste Policy Act of 1982 (NWPA) have weakened the social consensus about waste policy that existed...
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...
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...
Systems Engineering Applied to a Regulatory Program
The Nuclear Waste Policy Act directs the Nuclear Regulatory Commission to complete the licensing hearing process for the High-Level Radioactive Waste Geologic Repository within three years,...
Implementation of NUREG 1318 Guidance Within the Yucca Mountain Project
The U. S. Department of Energy's Yucca Mountain Project is implementing a quality assurance program that fulfills the requirements of the U. S. Nuclear Regulatory Commission...
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,...
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