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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'...

Safety Assessment of Radioactive Waste Disposal: A Priority Area for International Co-operation Within the OECD Nuclear Energy Agency
The OECD/NEA programme in the radioactive waste management area gives a high priority to long-term safety aspects of radioactive waste disposal practices. Overall aims of this part of...

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...

⁴⁰Ar/?⁹Ar Laser Fusion and K-Ar Ages From Lathrop Wells, Nevada, and Cima, California: The Age of the Latest Volcanic Activity in the Yucca Mountain Area
K-Ar and ⁴⁰Ar/³⁹Ar ages from the Lathrop Wells volcanic center, Nevada, and from the Cima volcanic field,...

Science Education: Critical Link to Nuclear Waste Disposal and Management
The management and disposal of municipal, industrial, hazardous, and radioactive wastes have become critical public issues in the 1990s. In many cases, companies in the waste disposal...

Determination of Diffusivities of Sorbing and Nonsorbing Species in Rocks
Through-diffusion experiments were performed for the sorbing and nonsorbing species in granites. Determining methods of diffusivities were discussed according to sorption properties of...

Interpretative Modelling of Studies of Sorption of Radionuclides onto Geological Materials
An integrated modelling and experimental approach related to the quantification of the sorption of radionuclides onto geological materials is described. The primary role of the experimental...

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...

How Much Must the Geologic Barrier Contribute to Safe HLW Disposal?
As a prerequisite of a potential repository site, it is important to assess the role of each system component in providing safety and, in particular, to establish the specific geological...

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...

State Environmental Review of a Proposed Utility Independent Spent Fuel Storage Installation
This paper describes the environmental review process which was applied by the State of Minnesota to a proposed dry cask storage facility. An environmental analysis of the proposed project...

Predicted Thermal and Stress Environments in the Vicinity of Repository Openings
An understanding of the thermal and stress environment in the vicinity of repository openings is important for preclosure performance considerations and worker health and safety considerations...

Unintentional Stoppages of Trucks Hauling High-Level Nuclear Waste in Nevada
Any unintentional stoppage of trucks hauling high-level nuclear waste in Nevada could intensify public concerns about the negative impacts of the Yucca Mountain project. This paper provides...

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...

 

 

 

 

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