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The Results of Near-Field Thermal and Mechanical Calculations of Thermal Loading Schemes
Two waste emplacement schemes, borehole and in-drift, are under evaluation as potential repository drift geometries for the Yucca Mountain Site Characterization Project. Calculations were...

Systems Implications of Repository Thermal Loading
A study was conducted to determine if implementation of a hot, cold or intermediate repository thermal loading strategy would have specific impacts on the overall Civilian Radioactive...

Spent Fuel Assembly Source Term Sensitivity Parameters: SAND92-2113C TTC-1225
Containment of cask contents by a transport cask in a function of the cask body, one or more closure lids, and various bolting, hardware, and seals associated with the cavity closure and...

Investigation in 3-D of Stress Distribution in a Circular Tunnel and Vertical Emplacement Holes Due to Thermal and Overburden Loading in Tuff
Thermal stress and displacement analysis using two 3-D finite element models, one having a course mesh and one having a highly detailed mesh are presented. Results are compared to those...

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...

Hydropulse Tomography for Identifying 3-D Permeability Distribution
For the purpose of identifying subsurface permeability distribution, a geotomographic method named Hydropulse Tomography (HT) was developed. As observation data, HT uses hydraulic pressure...

Determination of Water Content in Unsaturated Flow Experiments Using TDR and Capacitance
Electromagnetic techniques have been used for many years for the determination of moisture content in materials. We are adapting two of these techniques to the estimation of moisture in...

ATW System Impact on High-Level Waste
Criteria are developed for transmutation system impact on HLW storage that are related to intrusion and long-term risk reduction. Thermal reactor, fast reactor, and accelerator-driven,...

Reliability Modeling of an Engineered Barrier System
The Weibull distribution is widely used in reliability literature as a distribution of time to failure, as it allows for both increasing failure rate (IFR) and decreasing failure rate...

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...

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...

The Best of Both Worlds: Integrating Statistical and Deterministic Approaches to Area Remediation
We seek a complete framework for adaptive area characterization for purposes of remediation, incorporating both statistical and deterministic features. This hybrid methodology involves...

A Comparison of Geostatistically-Based Inverse Techniques for Use in Performance Assessment Analyses at the WIPP Site?Results from Test Case No. 1
The groundwater flow pathway in the Culebra Dolomite aquifer at the Waste Isolation Pilot Plant (WIPP) has been identified as a potentially important pathway for radionuclide migration...

Surface Complexation Model Prediction of Np and Pu Distribution Coefficients
Robust estimates of radionuclide sorption coefficients (K_d) are needed to estimate radionuclide retardation during ground-water transport from a...

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...

Functional Analysis of the Exploratory Studies Facility
This paper discusses the development of the 'Physical System Requirements-Exploratory Studies Facility' (PSR-ESF) document. Based on a functional analysis approach, this document includes...

Safeguards and Security Issues at the MRS Facility
The U.S. Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is responsible for disposing of the nation's high level radioactive waste in a way that ensures...

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...

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...

 

 

 

 

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