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...
Dry Spent Fuel Storage Compatibility at the Back End of the Fuel Cycle
The U.S. Nuclear Regulatory Commission (NRC) has publicly called for dry storage designs to be compatible with the back end of the fuel cycle, to achieve overall fuel cycle efficiency....
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...
The Continuing Evolution of a Radioactive Material Transport System
The paper considers the evolution of BNFL's transportation system and those lessons learned and incorporated or being incorporated in the system as it continues to evolve....
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)....
Certification Challenges in the Development of an Innovative High Payload Capacity Spent Fuel Transportation Cask
The design approach and certification strategy used in the development of an innovative transportation cask for legal weight truck shipments of spent nuclear fuel is presented. The proposed...
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...
Operational Considerations in Specifying Legal Weight Vehicles for the Highway Transport of Spent Nuclear Fuel
This paper presents the results of a research project in which tractor manufacturers and carrier companies were interviewed to gather information on operational concerns in specifying...
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...
Three-Dimensional Plume Dynamics in the Vadose Zone: PORFLO-3 Modeling of a Defense Waste Leak at Hanford
In 1973, approximately 450 m3 of liquid containing radioactive and chemical wastes leaked from the 241-T-106 single-shell tank into the vadose zone...
Permeability and Dispersivity of Variable-Aperture Fracture Systems
A number of recent experiments have pointed out the need of including the effects of aperture variation within each fracture in predicting flow and transport properties of fractured media....
A Stratified Percolation Model for Saturated and Unsaturated Flow Through Natural Fractures
The geometry of the asperities of contact between the two surfaces of a fracture and of the adjacent void spaces determines fluid flow through a fracture and the mechanical deformation...
Study of Fractal Aperture Distribution and Flow in Fractures
This study examines the roughness profiles and aperture distributions of fractures and faults by using concepts from fractal geometry. Simple models of flow of fluid in rough fractures...
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...
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