Keeping Lifelines Alive
There were no city water supplies to fight the fires in San Francisco after last year's earthquake. The fires were brought under control because of an historic auxiliary water...
Shop Drawings: In Need of Respect
Engineer Robert L. Boehmig voices his concerns regarding the preparation of structural shop drawings. He gives his view of the shop drawing's role in construction projects,...
Natural Radionuclides in Groundwater From J-13 Well at the Nevada Test Site
The concentrations of U-238 and Th-232 chain members are extremely low in J-13 water, suggesting that their concentrations in groundwaters are largely governed by sorption/desorption processes....
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...
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....
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...
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...
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)...
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,...
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....
Fluid Behavior Considerations for Waste Management in Low-Gravity Environments
Design of waste recycling systems for spacecraft requires a knowledge of fluid behavior in microgravity. As gravity is reduced, phenomena usually ignored in the One-G environment of earth...
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