Critical Stresses in Nuclear Waste Container Under Normal Handling Conditions
Critical stresses in the pintle, flat tophead, canister shell, the bottom plate and in the weldment of a high level nuclear waste canister are evaluated under a variety of static and dynamic...
Evaluating Soil Moisture and Hydraulic Conductivity in Semi-Arid Rangeland Soils
The United States Department of Energy's Office of Civilian Radioactive Waste Management (DOE-OCRWM) Fellowship Program supports various disciplines of academic research related to the...
Development of 3-D Lithostratigraphic and Confidence Models at Yucca Mountain, Nevada
Computerized three-dimensional geologic models of potential high-level nuclear waste repositories such as Yucca Moutain, Nevada, are important for visualizing the complex interplay of...
Connectivity and the Continuum Approximation in Fracture Flow Modeling
The continuum assumption is frequently made when modeling flow in fractured media. The approach presented in this paper helps evaluating the validity of such an assumption. Two indices...
Characterizing the Hydrogeologic Framework of the Death Valley Region, Southern Nevada and California
Three-dimensional (3-D) hydrogeologic modeling of the complex geology of the Death Valley region requires the application of a number of Geoscientific Information System (GSIS) techniques....
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...
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...
Application of Discrete Event Simulation to MRS Design
The application of discrete event simulation to the Monitored, Retrievable Storage (MRS) material handling operations supported the MRS conceptual design effort and established a set of...
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...
A Systematic Human Factors Assessment of a Department of Energy Facility
This paper presents the methodology for conducting a systematic human factors assessment of the as-built configuration of buildings at the Rocky Flats Plant (RFP). In support of this effort,...
Optimizing Human Reliability: Mock-Up and Simulation Techniques in Waste Management
This presentation describes an ongoing effort to incorporate human factors principles into the design and process development for waste management programs at a nuclear weapons plant....
Subsurface Transport of Radioactive Material Using Adaptive Finite Elements
A finite element method which utilizes mesh adaptation is used to calculate transient groundwater flow and pollutant transport. Mass lumping and reduced integration are employed to enhance...
Modeling of Saturated Zone at Yucca Mountain, Nevada
This paper presents preliminary results of groundwater modeling of the saturated zone in the vicinity of Yucca Mountain. The analysis used both a regional (approximately 250 ? 250 km)...
Integrated Test Evaluation Decision Framework for the Yucca Mountain Project
An Integrated Test Evaluation decision framework and computer model were developed to help prioritize site-characterization tests at Yucca Mountain. An initial application of the framework...
Software Quality Assurance on the Yucca Mountain Site Characterization Project
The Yucca Mountain Site Characterization Project (YMP) has been involved over the years in the continuing struggle with establishing acceptable Software Quality Assurance (SQA) requirements...
Thermal-Hydraulic Analyses of Molten Glass in a Joule-Heated Melter
Physical modelling using glycerine and three-dimensional mathematical modelling were executed to study temperature and flow profiles of molten glass in the melter for the vitrification...
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...
Heat Transfer in Vertical Concentric Cylinders in a High Level Nuclear Waste Repository
Modeling free convection heat transfer in an cylindrical annular enclosure is still an active area of research and an important problem to be addressed in the high level nuclear waste...
Structure of Crater Flat and Yucca Mountain, Southeastern Nevada, as Inferred from Gravity Data
Existing gravity data in the vicinity of Yucca Mountain and Crater Flat have been examined to determine if these data support only the caldera model or if they support other geologic models...
Return to search