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...

Spent Fuel Waste Form Characteristics: Grain and Fragment Size Statistical Dependence for Dissolution Response
The Yucca Mountain Project of the U.S. Department of Energy is investigating the suitability of the unsaturated zone at Yucca Mountain, NV, for a high-level nuclear waste repository. All...

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...

Gaseous Release of Carbon-14: Why the High Level Waste Regulations Should be Changed
The high-level nuclear waste regulations pertaining to gaseous release of carbon-14 from a repository should be changed to allow greater release, for several reasons. Some of them are...

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...

Removal of Dissolved and Suspended Radionuclides from HWVP Liquid Wastes
It was determined during Preliminary Design of the Hanford Waste Vitrification Plant that certain intermediate process liquid waste streams should be decontaminated in a way that would...

Properties of Solidified HLW and Their Changes Under Storage and Disposal Conditions
The paper gives the results of the studies of the properties of different solidified high level waste (HLW) - vitreous (phosphate and borosilicate) composites as well as glass ceramics...

Developing an Education Program for Schools on Radioactive Waste Management
United Kingdom Nirex Limited is responsible for the development of a deep disposal facility for Britain's solid low and intermediate-level radioactive wastes. In line with...

Curriculum and Instruction in Nuclear Waste Disposal
Curriculum and instruction in nuclear waste disposal is part of the larger problem of curriculum and instruction in science. At a time when science and technological literacy is crucial...

Radionuclide Migration as a Function of Mineralogy
The migration of radionuclides is studied as a function of mineralogy utilizing batch sorption and column experiments. The transport behavior of alkaline, alkaline-earth, and transition...

Effect of Material Heterogeneities on Flow Through Porous Media
Modeling studies were conducted to determine the effects of material heterogeneities on the flow of water through rock. Multiple numerical calculations were made using random variations...

Modelling of Hydro-Thermo-Mechanical Effects in a Fracture Intersecting a Nuclear Waste Deposition Hole
The groundwater flow in a vertical fracture intersecting a hypothetical nuclear waste deposition hole was examined. After excavation and emplacement of the nuclear waste canister, the...

 

 

 

 

Return to search