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...
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...
Combined Analytical/Numerical Approaches to Solving Fluid Flow Problems in the Unsaturated Zone at Yucca Mountain
Various analytical and numerical approaches are presented for the study of unsaturated flow processes in the vicinity of the Yucca Mountain, Nevada, the proposed site of an underground...
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....
The Status of the Site Characterization and Validation Program in Phase III of the OECD/NEA Stripa Project
In 1980, the International Stripa Project was organized under the aegis of the OECD Nuclear Energy Agency for the purpose of conducting research, at the Stripa mine in Sweden, related...
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....
Modeling of Coupled Heat-Mass-Stress Effects in Geologic Media
To investigate the importance of coupled hydraulic-thermal-mechanical processes for the potential nuclear waste storage repository at the Yucca Mountain, a computer code is being developed....
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...
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...
Applications of Fracture-Flow Modeling to Site Characterization
This paper describes practical applications of discrete-fracture approaches for design and analysis of groundwater flow about high-level radioactive waste repositories. The paper presents...
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)...
Development of a CRUD Particle Size Distribution and Its Effect on Cask Source Term and Containment Analyses
Spent pressurized-water reactor (PWR) and boiling-water reactor (BWR) fuel rods from three reactors were examined by hot cell periscope, energy dispersive x-ray analysis, and scanning...
The Expected Condition of Spent LWR Fuel on Delivery to a Repository
The condition of spent fuel on delivery to a repository is affected by its service in the reactor and by the postirradiation activities including wet and dry storage; fuel examination,...
Fluid Line Deployment and Repair for Space Station
Deployment of the utility system for providing services to the NASA Space Station Freedom provides a unique challenge in design and material technology. The system must be lightweight,...
Global Problems: Implementing Mission to Planet Earth
Serious global environmental problems are facing our generation on Earth. The decrease in ozone concentrations and the greenhouse effect have implications for all life forms on the planet....
Conceptual Design for a Lunar-Base CELSS
Future human exploration is key to the United States National Space Policy goal of maintaining a world leadership position in space. In the past, spacecraft life support systems have used...
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