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'...
Development of the ASME/NUPACK Code
A Committee has been active for 10 years to develop Code rules for the design, construction and in-service requirements of containment systems for nuclear spent fuel and high level radioactive...
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...
Multiple Event Considerations for Postclosure Seismic Hazard Evaluations at Yucca Mountain, Nevada
Postclosure waste canister design requirements suggest the values used for seismic design have less than a 10% chance of being exceeded in a 1,000 year postclosure period. Considerably...
Design Control Overview fot the Yucca Mountain Site Characterization Project Exploratory Shaft Facility
This paper presents an overview of the design control process used for the Exploratory Shaft Facility (ESF) at Yucca Mountain. Design and design control is a complex, often iterative,...
Design Considerations for the Yucca Mountain Project Site Characterization
The Site Characterization Facilities (SCF) to be located in volcanic tuff at Yucca Mountain is a challenge to manage, design, and construct. This challenge is a result of a number of factors....
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...
Conceptual Design Study of Geological Disposal System of High-Level Waste
Conceptual design study of geological disposal system for HLW was carried out taking into account geological environment in Japan, in order to provide disposal concepts for integrated...
Flow and Transport Around a Noncontinuous Horizontal Layer at Yucca Mountain
Computer simulations were used to examine the effect of a noncontinuous horizontal layer on the flow field and contaminant transport of a simplified conceptual model. The domain consisted...
Unsaturated Flow Through a Variable Aperture Fracture in Topopah Spring Welded Tuff
The role of fractures in unsaturated flow through welded and nonwelded tuffaceous rocks is a fundamental question being addressed in performance assessment activities for the Yucca Mountain...
Transportation of Radioactive Materials Routing Analysis: The Nevada Experience
In 1987, the Nevada State Legislature passed a Bill requiring the Nevada Department of Transportation to develop and enforce a plan for highway routing of highway route controlled quantity...
Industry Experience and Programs that Benefit the Monitored Retrievable Storage (MRS) Facility Design
The design objectives and criteria for an MRS must be responsive to the needs and concerns of the public and the industry. It is shown here that to the maximum extent, existing industry...
Mechanistic Interpretation of Glass Reaction: Input to Kinetic Model Development
Actinide-doped SRL 165 type glass was reacted in J-13 groundwater at 90?C for times up to 278 days. The reaction was characterized by both solution and solid analyses. The glass was seen...
Potential Uses of Lead in Nuclear Waste Disposal
In order for lead to be considered as a nuclear waste packaging material, it must be shown that it has adequate corrosion resistance, and that it does not degrade the properties of other...
Modelling Studies for the Assessment of the Advanced Cold Process Canister
The Advanced Cold Process Canister (ACPC) is a new concept for the encapsulation of spent nuclear fuel for geological disposal. It consists of steel canister encased in a copper overpack....
Validation of Source-Term Models Using Natural Analogues
A comparison is made between the predicted distribution of copper calculated by the AREST source-term code and the measured profiles for copper surrounding a bronze cannon that was emplaced...
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