The Effect of Certain Assumptions on the Number and Type of Spent Fuel Casks Required 1998-2000
The Office of Civilian Radioactive Waste Management M&O contractor is determining the number of spent fuel transportation cask systems required to transport fuel from reactors...
Systems Integration and Economic Aspects of the Universal Container System
Universal containers (UC) are multi-assembly spent fuel containers that are loaded and sealed at reactor sites or the first DOE facility. They are thereafter handled as clean containers...
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...
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...
Conceptual Design of a Monitored Retrievable Storage Facility
In order to achieve timely acceptance of spent nuclear fuel into the federal radioactive waste management system and to limit the amount of additional at-reactor storage capacity that...
Demonstration of a Transportable Storage System for Spent Nuclear Fuel
The ultimate disposal of spent nuclear fuel is a major issue that continues to plague the nuclear industry and the Department of Energy (DOE). In an effort to resolve some of the outstanding...
Evaluation of Spent Fuel Behavior Under Interim Storage Conditions in Russia
The nuclear power in Russia is based on three types of water cooled power reactors VVER-440, -1000 and RBMK-1000. Two fast sodium cooled reactors-prototypes BN-350 and BN-600 are in commercial...
Assessments of System Impacts of Spent Fuel Thermal Characteristics and Emplacement Rates
Analyses conducted to evaluate the impacts spent fuel thermal characteristics and emplacement rates might have on the thermal conditions in a candidate geologic repository at the Yucca...
Shielding Benchmark Calculations of Selected Spent Fuel Storage Cask Experiments
This paper describes the application of the three-dimensional Monte Carlo code MORSE-SGC, as implemented in the SCALE system calculational sequence SAS4, to the analysis of a series of...
Verification of Shielding Analysis for Spent Fuel Storage Casks
Casks of type CASTOR are used for transport and storage of spent LWR fuel assemblies. The purpose of the present work is the verification of shielding design analysis methods by application...
Non-Fuel Bearing Hardward Melting Technology
Battelle has developed a portable hardware melter concept that would allow spent fuel rod consolidation operations at commercial nuclear power plants to provide significantly more storage...
Consolidating BWR Non-Fuel Bearing Components (NFBC)
Nuclear Assurance Corporation (NAC), in cooperation the with Empire State Electric Energy Research Corporation (ESEERCO) and the Electric Power Research Institute (EPRI), has been developing...
Feasibility Assessment Grants in Support of Volunteer Siting of a Monitored Retrievable Storage Facility
The Monitored Retrievable Storage facility (MRS) is an integral component of the planned Federal radioactive waste management system. The MRS will temporarily store spent fuel from commercial...
Summary of Revised Potentiometric-Surface Map for Yucca Mountain and Vicinity, Nevada
The revised map for the potentiometric surface of the uppermost saturated zone in Tertiary volcanic rocks at Yucca Mountain, Nevada, is based mainly on 1988 water levels. Refinement of...
Groundwater Flow Modelling for the TVO-92 Safety Analysis of Spent Fuel Disposal
The TVO-92 safety analysis of spent fuel disposal is based on preliminary site investigations carried out at five sites in Finland between 1987 and 1992. Groundwater flow analyses have...
Application of Quality Assurance to Site Characterization
Siting studies for nuclear power plants are conducted for the purpose of determining the suitability of the site (a natural system) on plant systems that prevent the release of radioactive...
Potential Nuclear Material Safeguards Applied to the Department of Energy's Civilian Radioactive Waste Management System
The Office of Civilian Radioactive Waste Management (OCRWM) within the U.S. Department of Energy is charged with the responsibility of safe and efficient disposal of this Nation's civilian...
A Numerical Analysis of Spent Nuclear Fuel Thermal Characteristics
A numerical analysis is presented comparing the thermal behavior of a spent boiling water reactor fuel pin and an electric heating element intended to simulate the fuel pin in an experimental...
Numerically Predicting Horizontally Oriented Spent Fuel Rod Surface Temperatures
A comparison between numerical calculations with use of commercial thermal analysis software packages and experimental data simulating a horizontally oriented spent fuel rod array was...
A Homogeneous Equilibrium Model for Analysis of Spent Fuel Shipping Containers
Transportation of nuclear spent fuel is inevitable over the coming years. However, in order to ensure the safety of such transport, computational models must be established, which are...
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