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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...

Comparative Analyses of Spent Nuclear Fuel Transport Modal Options
The movement of nuclear waste can be accomplished by various transport modal options involving different types of vehicles, transport casks, transport routes, and intermediate intermodal...

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,...

Size and Transportation Capabilities of the Existing U.S. Cask Fleet
This study investigates the current spent nuclear fuel cask fleet capability in the United States. In addition, it assesses the degree to which the current fleet would be available, as...

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...

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...

Research for Final Disposal of Unreprocessed Spent Nuclear Fuel in Sweden
The second Swedish programme on research, development and demonstration in the nuclear radioactive waste management area was submitted by SKB to the Swedish National Board for Spent Nuclear...

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...

Study of an Alternativefor Repository of Radioactive Waste?Taiwan Case
The accumlation of spent fuel and radioactive waste is forcing producers to look for repository systems in Taiwan. Tectonic setting, and geologic processes indicate that the Penghu Islands...

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...

Social Issues and Challenges in the Disposal of Nuclear Waste
Equity and the perception of fairness are issues equal in importance to technical validity in the development of high-level waste management programs. With the passage of the Nuclear Waste...

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....

Evaluating and Controlling the Characteristics of the Nuclear Waste in the FWMS Using Waste Stream Analysis Model
The Waste Stream Analysis (WSA) Model is used by the Department of Energy to model the time and location dependent properties of the nuclear waste stream in the Federal Waste Managements...

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...

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...

Effects of Water Composition on the Dissolution Rate of UO₂ Under Oxidizing Conditions
Dissolution rates were measured on crushed unirradiated UO₂ fuel pellet samples under oxidizing conditions using a flow-through testing method. Water...

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,...

The Role of the U.S. Nuclear Waste Technical Review Board
The Nuclear Waste Technical Review Board is a new independent governmental establishment with in the Executive Branch created in December 1987 when Congress enacted the Nuclear Waste Policy...

Incident Solar Flux at Fixed Orientations
Optimal orientations are computed to maximize or minimize the incident solar flux onto surfaces on spacecraft at fixed attitudes. This analysis was motivated by a potential need to optimize...

 

 

 

 

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