Approximate Preliminary Methods for Design of Lateral Load Resisting Systems in High Rise Buildings
A new group of optimization programs uses the speed and power of modern computers to eliminate the need for guessing preliminary sizes. Starting with any arbitrary sizes and a fixed geometry,...
Verification of Advanced Analysis Techniques
As a designer there is a concern over the complexity of analysis required by design specifications and building codes because it forces engineers into types of analysis for which many...
Analysis and Design of Structures with Outrigger Arms
Although sophisticated computer methods are available for analyzing an entire building structure, there is a need for simplified methods (a) for checking the accuracy of the computer analyses,...
Verification of Approximate Methods of Structural Analysis
Sophisticated computer programs for the determination of the effects of instability on the inelastic stress resultants in steel structures will appear to be 'black boxes'...
Certifying the TN-BRP and TN-REG Transportable Storage Demonstration Casks
The U.S. Department of Energy (DOE) has obtained U.S. Nuclear Regulatory Commission (NRC) certification to transport two transportable storage casks for a demonstration project. Because...
Development of the GA-4 and GA-9 Legal Weight Truck Spent Fuel Shipping Casks
General Atomics (GA) is developing two legal-weight-truck spent-fuel shipping casks for transporting commercial reactor spent fuel. The GA-4 pressurized-water-reactor (PWR) and the GA-9...
High-Capacity, High-Strength Trailer Designs for the GA-4/GA-9 Casks
General Atomics (GA) is developing final designs for two dedicated legal-weight trailers to transport the GA-4 and GA-9 Spent-Fuel Casks. The basic designs for these high-capacity, high-strength...
Design Control Process Requirements for Geologic Repository Operations Area Design
This paper outlines U.S. Nuclear Regulatory Commission's (NRC's) key regulations applicable to U.S. Department of Energy's (DOE's) design...
Interpretation and Modelling Process of Bedrock Structures for Site Evaluation in Finland
The repository site for the final disposal of spent nuclear fuel in Finland will be selected by the end of the year 2000. Preliminary site investigations have been made in five areas since...
Mechanical Anisotropy of the Yucca Mountain Tuffs
Three series of measurements were performed on oriented cores of several Yucca Mountain tuffs to determine the importance of mechanical anisotropy in the intact rock. Outcrop and drillhole...
Application of Discrete Feature Analysis to Repository Characterization
Rock mass heterogeneity plays an important role in the hydrologic and mechanical behavior of radioactive waste repositories. This heterogeneity is, in turn, strongly influenced by the...
Fractal Characteristics of Fracture Roughness and Aperture Data
In this study mathematical expressions are developed for the characteristics of apertures between rough surfaces. It shown that the correlation between the opposite surfaces influences...
Design and Operating Criteria of the French Deep Repository for High Level Radioactive Waste
The design and operating criteria of the French geologic repository for high level radioactive waste (HLW) were selected for their contribution to operational and long-term safety, as...
A Probe Method for Measuring In Situ Rock Thermophysical Properties
The application of a thermal probe method for in situ thermophysical property measurement is analyzed. The REKA method (Rapid Evaluation of k and alpha) involves a single-borehole probe...
Correlation of Hydraulic Conductivity and Sonic Velocity in Water-Saturated Tuff
A laboratory study was conducted to investigate the correlation of hydraulic and sonic properties of water-saturated tuff. The hydraulic test used a new rock block testing machine, which...
An Approach to Evaluate the Sufficiency of Highway Bridges for Nuclear Spent Fuel Transportation
The transportation of radioactive spent fuel can have a significant impact on bridge structures located on designated routes. Due to the critical nature of the cargo and because of the...
Disposal of Vitrified Waste in an Unsaturated Environment
An experimental program is described wherein the effect of important independent variables on glass reaction under conditions that may exist for unsaturated storage is examined. The effect...
Development of a Structural Model to Analyze Public Opinion on a High-Level Radioactive Waste Facility
Studies show that Nevada residents and state officials oppose the proposed high-level radioactive waste repository project at Yucca Mountain. Nevada residents view the Yucca Mountain repository...
Field Investigations for Seismic Effects on Mechanical and Geohydrologic Response of Underground Structures in Jointed Rock
An exploratory Seismic Rock Mechanics research program has been initiated by the U.S. Nuclear Regulatory Commission at the Center for Nuclear Waste Regulatory Analyses (CNWRA) to study...
Research Program to Develop and Validate Conceptual Models for Flow and Transport Through Unsaturated, Fractured Rock
As part of the Yucca Mountain Project, our research program to develop and validate conceptual models for flow and transport through unsaturated fractured rock integrates fundamental physical...
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