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Radionuclide Transport in Fractured Media
Until recently, the classical advective-dispersive transport equation was considered to be an adequate model for describing the motion of a solute (e.g. radionuclides) in porous and fractured...

An Object Oriented Relational Database for Assessing Radioactive Material Transport
EnviroView is an object oriented relational database used for inventory control and monitoring locations of radioactive and toxic materials. Visual images of local sites, building locations,...

Disposal of Defense Spent Fuel and HLW from the Idaho Chemical Processing Plant
Acidic high-level radioactive waste (HLW) resulting from fuel reprocessing at the Idaho Chemical Processing Plant (ICPP) for the U. S. Department of Energy (DOE) has been solidified to...

Plutonium and Minor Actinide Transmutation by Long Irradiation in LWR
An investigation was made on the conceptual possibility of burning in a thermal reactor MOX fuel together with special pins containing plutonium, minor actinides and long-lived fission...

Remote Spent Fuel Handling in France at the La Hague Cask Unloading Facility
French policy for the back end of fuel cycle is based on spent fuel reprocessing. Irradiated spent fuels are transferred in casks from the nuclear reactors to the reprocessing plant where...

Photothermal Deflection Spectroscopy Investigations of Uranium Electrochemistry
Photothermal deflection spectroscopy (PDS) has been successfully applied to the study of uranium oxide electrochemistry. A brief description of PDS and preliminary results that demonstrate...

Treatment of Non Fuel Bearing Scrap
Problems encountered with the processing of irradiated non fuel bearing components (NFBC) during several rod consolidation demonstration programs identified the need to conduct further...

Non-Fuel Bearing Hardward Melting Technology
Battelle has developed a portable hardware melter concept that would allow spent fuel rod consolidation operations at commercial nuclear power plants to provide significantly more storage...

Recent Developments in Stochastic Modeling and Upscaling of Hydrologic Properties in Tuff
A set of detailed geostatistical simulations of porosity has been produced for a layered stratigraphic sequence of welded and non-welded volcanic tuffs at Yucca Mountain, Nevada. The simulations...

Stochastic Simulation of Mass Transport in Heterogeneous Formations Using Hard and Soft Conductivity Data
The mass transport in a synthetic 2-D heterogeneous formation is simulated through the Monte-Carlo method using continuum approach. The simulated hydraulic conductivity field are generated...

Significance of Geochemical Characterization to Performance at Yucca Mountain, Nevada
The U.S. concept for permanent disposal of high-level radioactive waste resembles those of other countries in that it relies upon burial in a deep geologic medium. This concept relies...

Modeling Adsorption of Mixtures of Radionuclides by Zeolitized Tuff
Multi-solute sorption isotherms were measured using 'nonscents', a zeolitized volcanic tuff material from Southeast Arizona. Isotherms for the three constituent binaries, Sr-Co, Cs-Sr...

Fission Product Distribution in Nuclear Test Cavities/Chimneys
When a nuclear device is exploded, residual radioactive material is distributed throughout the resulting underground cavity and rubble chimney. Refractory materials are more concentrated...

Research at Howard University on Retardation of Radionuclides by Sorption Processes During Host Rock?Ground Water Interactions
Extensive sorption measurements were made over a period of several years, of major radionuclides in J-13 Well water with Yucca Mountain tuff samples. Most of these measurements were single...

Diffusion of Sorbing and Non-Sorbing Radionuclides
Diffusion is considered one of the most important retardation mechanisms in fractured media. The diffusion experiments conducted involved solid tuff and groundwater from Yucca Mountain....

Surface Complexation Model Prediction of Np and Pu Distribution Coefficients
Robust estimates of radionuclide sorption coefficients (K_d) are needed to estimate radionuclide retardation during ground-water transport from a...

Open Channels in Fractures Maintained by Deposition and Erosion of Colloids
Colloids initially suspended in the water in fractures can deposit onto the fracture surfaces, and will partially or fully clog the fracture. The amount of clogging will depend on whether...

Late Quaternary History and Uranium Isotopic Compositions of Ground Water Discharge Deposits, Crater Flat, Nevada
Three carbonate-rich spring deposits are present near the southern end of Crater Flat, NV, approximately 18 km southwest of the potential high-level waste repository at Yucca Mountain....

Subsurface Transport of Radioactive Material Using Adaptive Finite Elements
A finite element method which utilizes mesh adaptation is used to calculate transient groundwater flow and pollutant transport. Mass lumping and reduced integration are employed to enhance...

Application of Quality Assurance to Site Characterization
Siting studies for nuclear power plants are conducted for the purpose of determining the suitability of the site (a natural system) on plant systems that prevent the release of radioactive...

 

 

 

 

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