Standard Contract Issue Resolution Process: An Overview and Status
The Department of Energy has identified 35 issues associated with the Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Waste (10 CFR Part 961) which need to be resolved...
The DOE Waste Acceptance Process for the Vitrified High-Level Waste Form
Borosilicate glass from Defense HLW producers will be emplaced in the civilian radioactive waste repository. Vitrified HLW will be under production before the repository license application...
Status of Cask Procurement Strategy to Satisfy DOE/OCRWM Requirements
The Nuclear Waste Policy Act requires the development of a safe and efficient system to transport spent nuclear fuel to and within the Federal Waste Management System. This paper describes...
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...
Solute Transport Characteristics of Fractured Dolomite in Southern Nevada, USA
Recirculating tracer tests in fractured Cambrian dolomite beneath the Amargosa Desert revealed (1) and 83-percent increased in apparent dispersivity resulting from a two-percent increase...
Procurement Quality Engineering
The 'Procurement Quality Function' is an element of the Body of Knowledge of Quality Engineering, as defined by the American Society for Quality Control (ASQC). This paper describes the...
Throughput Rate Study
The Civilian Radioactive Waste Management System (CRWMS) Management and Operating (M&O) Contractor, has completed a study to analyze system wide impacts of operating the CRWMS...
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,...
The Waste Isolation Pilot Plant (WIPP) Integrated Project Management System
The Waste Isolation Pilot Plant (WIPP), located 26 miles east of Carlsbad, New Mexico, is a research and development project of the Department of Energy (DOE), tasked with the mission...
Recent Management Experience of UK Performance Assessments of Radioactive Waste Disposal
The approach to management used over the past decade by a UK Government regulatory body (HMIP) to develop, test and apply integrated risk assessment methods, using a team of private contractors,...
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...
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,...
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