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...
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)....
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...
Transportation Legend, Fact and Hysteria or, How to Dismantle a Mature Industry
In the rush to 'correct' the perceived deficiencies in the regulations covering the transportation of radioactive materials, many people, from legislators to...
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...
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...
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...
Optimizing the Spent Fuel Transportation Cask for Spent Fuel Age and Burnup: A Preliminary Analysis
The U.S. Department of Energy (DOE) has been assigned responsibility for managing the nation's spent nuclear fuel (SNF). Because of the large quantity of SNF to be moved,...
Transportation Cask Life Cycle Cost Uncertainty Analysis
This paper demonstrates an uncertainty analysis methodology using random sampling. This methodology has been applied to a nuclear waste transportation code, and several transportation...
Accident Analyses in Fulfillment of the Requirements of the National Environmental Policy Act and Their Relationship to the Packaging and Testing Requirements of the Nuclear Regulatory Commission
In planning its Transportation Program, the Office of Civilian Radioactive Waste Management must address two fundamental questions: (1) To what extent are the reasonably foreseeable significant...
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...
Computed Distributions of Residual Shaft Drilling and Drift Construction Water in the Exploratory Facilities at Yucca Mountain, Nevada
The Yucca Mountain Project is studying the feasibility of constructing a high-level nuclear waste repository at Yucca Mountain in southwest Nevada. One activity of site characterization...
Multi-Dimensional Modeling of Unsaturated Flow in the Vicinity of Exploratory Shafts and Fault Zones at Yucca Mountain, Nevada
Modeling studies were conducted to determine the potential effects of exploratory shafts on moisture distribution in the vicinity of an exploratory shaft facility, and the potential for...
Influence of High Burn Up Nuclear Fuel and MOX on the High Level Reprocessing Waste Management
This paper compares characteristics of high level waste issued from the reprocessing of high burn up fuel (HTC) and mixed oxide (U-Pu)O2 fuel (MOX)...
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