Evaluation of Near-Field Thermal Environmental Conditions for a Spent Fuel Repository in Tuff
A repository heat transfer analysis is being performed by the Pacific Northwest Laboratory (PNL)a for the U.S. Department of Energy's...

?4C Release From Failed Spent Fuel Containers
Partially failed containers may provide a meaningful barrier to the release of gaseous radionuclides. A modeling approach is outlined and sample calculations are provided that show the...

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....

The Continuing Evolution of a Radioactive Material Transport System
The paper considers the evolution of BNFL's transportation system and those lessons learned and incorporated or being incorporated in the system as it continues to evolve....

BR-100 Spent Fuel Shipping Cask Development
Continued public acceptance of commercial nuclear power is contingent to a large degree on the U.S. Department of Energy (DOE) establishing an integrated waste management system for spent...

Certification Challenges in the Development of an Innovative High Payload Capacity Spent Fuel Transportation Cask
The design approach and certification strategy used in the development of an innovative transportation cask for legal weight truck shipments of spent nuclear fuel is presented. The proposed...

Operational Considerations in Specifying Legal Weight Vehicles for the Highway Transport of Spent Nuclear Fuel
This paper presents the results of a research project in which tractor manufacturers and carrier companies were interviewed to gather information on operational concerns in specifying...

Systems Models for Predicting Radioactive Waste
This paper illustrates how a model can be constructed to analyze the growth of accumulated spent Light-Water-Reactor fuel using a technique from systems theory which has proved to be capable...

Deposition of Airborne Particles from Fractured Spent Fuel or High-Level Waste
Preliminary equations are developed to predict the amount of deposition of airborne particles that may result from an accidental release in a hot cell. The fraction of these airborne particles...

Evaluation of the Canadian HLW Disposal Program?Performance Assessment Aspects
The inception and development of the Canadian HLW disposal program are described, showing its basis in the multi-barrier system concept and noting the mechanisms in place for its evaluation...

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...

Investigation of Burnup Credit Allowance in the Criticality Safety Evaluation of Spent Fuel Casks
The payloads of present generation spent fuel casks are constrained by a criticality design basis that assumes loading with unirradiated fuel. This presentation discusses work in progress...

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,...

The Role of Sensor Directed, Model-Based Control in Robotic Handling of Nuclear Waste Casks and Materials
This paper discusses the results from several projects at Sandia National Laboratories investigating the application of intelligent machine technologies to remote handling of nuclear waste...

Spent Fuel and High-Level Waste Management in Selected Countries: Trends and Issues
This paper contains descriptions of the major parameters and plans for management of spent nuclear fuel and high-level radioactive wastes in Belgium, Canada, France, the Federal Republic...

Spent Fuel Storage Requirements for Nuclear Utilities and OCRWM
Projected spent fuel generation at U.S. power reactors exceeds estimated aggregate pool storage capacity by approximately 30,000 metric tons of uranium (MTU). Based on the current repository...

Site Selection Criteria for Constructing an Independent Spent Fuel Storage Installation (ISFSI) at a Commercial Nuclear Power Plant
Commercial nuclear power plants in the U.S. are responsible for providing their own interim storage for excess spent fuel. A facility located onsite, acting as a buffer between in-pool...

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,...

 

 

 

 

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