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International Safeguards Relevant to Geologic Disposal of High-Level Wastes and Spent Fuels
Spent fuels from once-through fuel cycles placed in underground repositories have the potential to become attractive targets for diversion and/or theft because of their valuable material...

MRS Systems Study, Task F: Transportation Impacts of a Monitored Retrievable Storage Facility
The passage of the Nuclear Waste Policy Amendments Act of 1987 (NWPAA) modified the basis from which the Office of Civilian Radioactive Waste Management (OCRWM) had derived and developed...

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...

Optimizing Spent Fuel Cask Designs for Use in the Federal Waste Management System
The DOE will design and develop a new fleet of casks to transport spent fuel using innovative approaches to optimize the cask design. Preliminary casks designs indicate capacity increases...

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...

TN28V High Capacity Cask for the Transport and Storage of Vitrified Wastes
When the option of reprocessing has been selected, closing of the fuel cycle implies the return shipment of reprocessing wastes back to the country of origin of the spent fuel, in particular...

Current Social Systems Issues in the U.S. High Level Waste Management Program
Major changes in the U.S. high level waste management program since passage of the Nuclear Waste Policy Act of 1982 (NWPA) have weakened the social consensus about waste policy that existed...

Permeability and Dispersivity of Variable-Aperture Fracture Systems
A number of recent experiments have pointed out the need of including the effects of aperture variation within each fracture in predicting flow and transport properties of fractured media....

Plans for Characterization of the Potential Geologic Repository Site at Yucca Mountain, Nevada
Site investigations in the vicinity of the potential repository site at Yucca Mountain, Nevada, have occurred for many years. This is due to the proximity of the potential repository site...

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...

What Will be the Engineered Barriers for Deep Disposal of High Level Radioactive Wastes in the Future?
Two sealing approaches are currently being developed in France for deep geological disposal of high-level wastes. One is based on the use of swelling clay in order to restore the initial...

The Analysis of Horizontal Cooling Enhancement for Nuclear Waste Container Emplacement
This paper presents a novel method for distributing the heat generated by waste containers emplaced in the proposed high-level nuclear waste site at Yucca Mountain, Nevada. The method...

Optimization Method for Dimensioning a Geological HLW Waste Repository
This method was developed by the CEA to optimize the dimensions of a geological repository by taking account of technical and economic parameters. It involves optimizing radioactive waste...

Defining the Need for and Functions of the Monitored Retrievable Storage (MRS) Facility
A series of system studies of the Civilian Radioactive Waste Management System were conducted by the Department of Energy (DOE) to determine the role for a Monitored Retrievable Waste...

Facility Interface Capability Assessment (FICA) Project
The U.S. Department of Energy-Office of Civilian Radioactive Waste Management (DOE-OCRWM) is sponsoring the Facility Interface Capability Assessment Project to determine current and potential...

Acceptance of Spent Fuel of Varying Characteristics
This paper is a preliminary overview of a study with the primary objective of establishing a set of acceptance selection criteria and corresponding spent fuel characteristics to be incorporated...

Experience with Certifying Borated Stainless Steel as a Shipping Cask Basket Material
The original cask designs for a cask demonstration project featured fuel baskets constructed of borated stainless steel (bss) as a structural material. The project is intended to demonstrate...

High Level Radioactive Waste Management at the Savannah River Site
This paper describes the High Level Radioactive Waste (HLW) generated at the Savannah River Site (SRS), outlines how it has been managed over the 35 years since site operations began,...

Programmatic Challenges and the Value of Testing on the West Valley Demonstration Project's Vitrification Facility Design
The primary objective of the West Valley Demonstration Project (WVDP) is the solidification of approximately 2.1 million liters (560 thousand gallons) of high-level waste (HLW) which resulted...

 

 

 

 

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