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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...

An Overview of the Vitrification of Defense High-Level Waste at the Hanford Site
Nearly 63 percent of the nation's high-level nuclear waste has accumulated at the U.S. Department of Energy's (DOE) Hanford Site in Washington State. This accumulation...

Sellafield?From High Level Notoriety to Intermediate Acceptance
After a highly publicised accident at Sellafield, involving radioactive pollution, a period of continuous adverse media coverage eroded public confidence in the plant and its operators,...

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...

Optimizing the Spent Fuel Transportation Cask for Spent Fuel Age and Burnup: A Preliminary Analysis
The U.S. Department of Energy (DOE) has been assigned responsibility for managing the nation's spent nuclear fuel (SNF). Because of the large quantity of SNF to be moved,...

Properties of the West Valley Waste Form
The centroid composition of the West Valley Demonstration Project waste form has been selected on the basis of criteria mandating high chemical durability and good processibility. A review...

Vapor Hydration and Subsequent Leaching of Transuranic-Containing SRL and WV Glasses
High-level nuclear waste glass that is subject to disposal in the proposed unsaturated environment at Yucca Mountain, Nevada, initially will be altered through contact with humid air....

The Technical Review Group: An Application of the Quality Assurance Program Descriptions for Defense High-Level Waste Processing
This paper describes the formation of a technical review group (TRG) as an early application of the quality assurance program for high-level waste processing. The objectives and functions...

The DWPF Product, and Its Qualification Program
The Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS) will be the first facility in the nation capable of immobilizing high-level nuclear waste. Production of DWPF...

Estimate of the Source Term for a Repository Surface Facility From the Routine Processing of Spent Fuel
The potential for release of radioactive material from the proposed handling and processing of spent nuclear fuel in a surface facility for a geologic repository was evaluated. The potential...

Effect of Minor Actinide Removal From Fission Products Before Vitrification on the Radiological Impact of a High Level Waste Deep Repository
The topic of this work is to assess the effect of minor actinide (Cm, Am, Np) removal from fission products before vitrification on the radiological impact of a vitrified waste geological...

The Source Term for HLW Disposal in the European Communities' R&D Programme
During the last five years, the EC's research programme on radioactive waste has focused much of its investigation in the field of HLW management on the source term for geologic...

Status of Site Investigations for Spent Fuel Repository in Finland
TVO's site programme aims at selection of a repository site for spent fuel by the end of 2000. A repository is planned to be constructed in the 2010's and commissioned...

Analysis of Requirements for Data and Information for the Management of Spent Nuclear Fuel Designated for Disposal in a Mined Geologic Repository
Official documents and relevant published papers were reviewed to determine what information on spent fuel will be needed by the Department of Energy (DOE) in order for it to meet its...

Characteristics of Potential Repository Wastes
The U.S. Department of Energy is responsible for the eventual disposal in a repository of spent fuels, high-level waste, and other radioactive wastes that may require long-term isolation....

Systems Integration Operations/Logistics Model (SOLMOD)
SOLMOD is a discrete event simulation model written in FORTRAN 77 and operates in a VAX or PC environment. The model emulates the movement and interaction of equipment and radioactive...

Incorporation of Reprocessing Raffinates and High Level Solids in Cement
Reprocessing highly enriched uranium fuel from UKAEA Materials Testing Reactors produces highly active aqueous raffinate. This is currently stored. The UK strategy is for raffinate immobilisation,...

High Level Waste Management at Sellafield
Reprocessing of irradiated nuclear fuel has been carried out at Sellafield since 1952, when reprocessing of fuel from the original UK air-cooled reactors began. In 1964 a second reprocessing...

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)...

Method for Determining the Fuel Contribution to the Source Term in Trasnport Casks
A comprehensive source term characterization methodology has been developed for the determination of the fuel contribution to the potentially releasable radioactivity in spent fuel shipping...

 

 

 

 

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