Optimal Route Selection for High Level Nuclear Waste Transport Based Upon Radiological Risk
The purpose of this paper is to demonstrate route optimization based directly upon the minimization of radiological risk as computed from local conditions. An operational impact analysis...
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...
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....
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...
Simulation of Heat Transfer in the Unsaturated Zone
It is well known that heat transfer can play an important roll in fluid flow near the emplacement site of high-level nuclear waste (K. Pruess and J.S.W. Wang, 1987). Heat transfer effects...
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,...
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...
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...
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...
Diffusion Coefficients and Hydraulic Conductivity in Unsaturated Hanford Soils and Sediments
Two groundwater transport parameters of some Hanford formation materials, the hydraulic conductivity and the diffusion coefficient, were measured to aid in predicting contaminant migration....
Prototype Heater Test of the Environment Around a Simulated Waste Package
This paper presents selected results obtained during the 301 day duration of the Prototype Engineered Barrier System Field Test (PEBSFT) performed in G-Tunnel within the Nevada Test Site....
Origin of Carbonate Deposits in the Vicinity of Yucca Mountain, Nevada: Preliminary Results of Strontium-Isotope Analyses
As part of the paleohydrology study of the Yucca Mountain Project, strontium-isotope analyses of carbonate deposits, ground water, and major rock reservoirs of strontium are in progress....
Reconnaissance ? ??C and ??8O Data from Trench 14, Busted Butte, and Drill Hole G-4, Yucca Mountain, Nevada Test Site
Trench 14 was excavated to investigate the extent of Quaternary movement on the Bow Ridge fault, a north-south structure on the east side of Yucca Mountain. The trench exposes calcite...
Dispute Resolution ? A New Approach for Public Acceptance of the High-Level Radioactive Waste Mamagement Regulatory System
This paper examines the feasibility of utilizing Dispute Resolution to significantly reduce the numbers of technical disputes subject to litigation in civil courts or before the NRC to...
Choosing AT-Reactor Spent Fuel Storage Technologies
Need for expansion of the spent fuel storage capability of reactor sites was first caused by delays in construction of reprocessing facilities, later by cessation of commercial reprocessing...
Recent Results on the Effect of Gamma Radiation on the Durability and Microstructure of DWPF Glass
The effect of gamma radiation on the durability and microstructure of a simulated nuclear waste glass from the Savannah River Site has been carefully investigated. Three large pieces of...
Systems Integration During the Development of a Federal Waste Management System
Systems integration in the development of the Federal Waste Management System for spent nuclear fuel and high-level radioactive waste involves not only the activities traditional to development...
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