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Spent Fuel Assembly Source Term Sensitivity Parameters: SAND92-2113C TTC-1225
Containment of cask contents by a transport cask in a function of the cask body, one or more closure lids, and various bolting, hardware, and seals associated with the cavity closure and...

Code Requirement for Concrete Repository and Processing Facilities
Because of varied uses and performance/safety requirements of concrete for high, medium and low level radioactive wastes, a review of the current ACI 349 Code document was carried out...

Inference of Moisture Content in Unsaturated Media Using Ultrasonics
This study focuses on the ability of commercial ulltrasonics equipment to determine the moisture content in unsaturated media. We are interested in the possible application of this technology...

A Working Definition of Scenario and a Method of Scenario Construction
The event-tree method of scenario construction has been chosen for the Yucca Mountain performance assessment. Its applicability and suitability to the problem are discussed and compared...

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,...

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...

Limited Work Authorization for a Monitored Retrievable Storage Facility
The issuance of an limited work authorization (LWA) by the Nuclear Regulatory Commission (NRC/Commission) allows a potential licensee permission to undertake preliminary site construction,...

Alternative Strategies?A Means for Saving Money and Time on the Yucca Mountain Project
The United States Department of Energy (DOE) is undertaking studies to determine the suitability of Yucca Mountain (YM) as a potential site for disposal of high-level nuclear waste. Yucca...

The Waste Isolation Pilot Plant (WIPP) Integrated Project Management System
The Waste Isolation Pilot Plant (WIPP), located 26 miles east of Carlsbad, New Mexico, is a research and development project of the Department of Energy (DOE), tasked with the mission...

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...

Using Co-Management in a Voluntary Hazardous Waste Facility Siting Process
The recent approval for construction and operation of a hazardous waste management facility in Manitoba, Canada is an example of a siting process that is voluntary and that gives the community...

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...

 

 

 

 

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