AREST: The Next Generation
Simple mass transport models using constant boundary conditions at the waste form surface and at the host rock boundary do not always results in realistic predictions of the performance...
Containment Barrier System Performance Assessment Modeling
A mathematical model to predict the cumulative failure distribution for the containment barrier system (CBS) employed in a deep geologic disposal facility is presented as a function of...
Maximum Individual Risks from Transported Spent Nuclear Fuel
The computer code TICLD (Transportation Individual Center Line Dose) is used with the computer code RADTRAN 4 to calculate maximum individual dose and risk from transportation accidents...
Operational Considerations in Drift Emplacement of Waste Packages
This paper discusses the operational considerations as well as the advantages and disadvantages of emplacing waste packages in drifts in a repository. The considerations apply particularly...
Waste Packager and Areal Power Density Approximator (WPA3) Computer Code
A microcomputer-based computer code called Waste Packager and Areal Power Density (APD) Approximator (WPA3) has been developed to compute waste package inventories and track individual...
An Assessment of Coupled Thermal-Hydrologic-Mechanical-Chemical Processes
A literature review was conducted to determine the state of knowledge available in the modeling of coupled thermal (T), hydrologic (H), mechanical (M), and chemical (C) processes relevant...
Findings of the Secretary of Energy Advisory Board Task Force on Radioactive Waste Management
Secretary of Energy James D. Watkins created the Task Force on Radioactive Waste Management in April 1991. He asked the group then to recommend measures the Department might take to strengthen...
The Role of Fault Zone in Affecting Multiphase Flow at Yucca Mountain
Within Yucca Mountain, the potential High Level Nuclear-Waste Repository site, there are large scale fault zones, most notably the Ghost Dance Fault. The effect of such high-permeability,...
Sensitivity and Probabilistic Analyses of Ground Water Travel Time in a Fractured and Variably-Saturated Geologic Medium
This paper presents a method for sensitivity and probabilistic analyses of performance of a hypothetical nuclear waste repository located in a layered, fractured, and variably-saturated...
Comparison of Predicted Far-Field Temperatures for Discrete and Smeared Heat Sources
A fundamental concern in the design of the potential repository at Yucca Mountain, Nevada is the response of the host rock to the emplacement of heat-generating waste. The thermal perturbation...
The Analysis of Repository-Heat-Driven Hydrothermal Flow at Yucca Mountain
To safely and permanently store high-level nuclear waste, the potential Yucca Mountain repository site must mitigate the release and transport of radionuclides for tens of thousands of...
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...
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