Computer Bound
The increasing use of computers in engineering design carries the danger that the software will be used incorrectly or only partially correctly. Engineers under pressure to reduce costs...
Dynamic Response Correlation of Cylindrical Tanks
The May 1983 Coalinga Earthquake provided an opportunity to correlate earthquake performance of cylindrical liquid storage tanks with behavior observed in laboratory shaking table experiments....
Seismic Evaluation of Non-Seismically Designed Existing Magnox Nuclear Power Plants
Special procedures included on-site testing with a portable shake table, low vibration testing using a structural dynamics analyser, and on-site inspections. The low vibration testing...
Update on Impact Effects in Nuclear Plants Part III?Review of Heavy Object Drop
The consequences of an accidental drop of a heavy component from a lifting device in a nuclear power plant are required to be evaluated even though the device may have been designed using...
Probabilistic Analysis of Impact Loading Conditions
Probabilistic methods are developed for the analysis of random impact loading conditions that arise from oblique, noncollinear, and spinning missile impacts. Models are developed for the...
Nonlinear Analysis of Reactor Vessel & Core Supports Subjected to Accidental Impact Loads
Nonlinear dynamic analyses of the reactor vessel, its support systems, the core and the core supports were performed to evaluate the consequences of such drops. Damage was defined in terms...
Computer-Aided Load Monitoring System for Nuclear Power Plant Steel Framing Structures
The design of nuclear power plant steel framing structures is a long and involved process. It is often complicated by numerous changes in design loads as a result of additions, deletions...
Computer-Aided Design (Seismic Qualification) of Cable Tray Support System ? CADSTrays
A computer system for the analysis and design of cable tray hangers for nuclear power generating plants is discussed. An interactive language for the CADSTrayS was developed. Application...
Sensitivity of Peak Dynamic Responses to Input Factors
Responses have been calculated for the Zion Unit 1 plant, using the SSMRP computer code SMACS, as part of the seismic probabilistic risk assessment performed by the Seismic Safety Margins...
Coupled Vertical-Rocking Response of Base-Isolated Structures
A base-isolated building can have a small horizontal eccentricity between the center of mass of the superstructure and the center of rigidity of the supporting bearings. The structure...
Techniques for Automating the Process of As-Built Reconciliation
The approach utilizes an electronic digital 'ruler' capable of measuring distances to 100 feet with a resolution of 1/100 of a foot. This ruler interfaces to...
Microcomputer Applications for NSSS Data Package Review
Associated with each component of a Nuclear Steam Supply System are the necessary supporting documents which demonstrate compliance with applicable codes, specifications and design criteria....
Design Verification of HVAC Duct Turning Vanes in Nuclear Power Plants
HVAC ducts in nuclear power plants utilize short radius elbow construction with turning vanes to minimize the space requirement for duct work and to reduce flow losses in the elbows. Turning...
A Correlation Study on the Spectrum Decomposition Method
The major elements of the Spectrum Decomposition Method (SDM) are reviewed together with its automated process for generation of in-equipment response spectra (IERS). The floor required...
Transient Fluid-Structure Interaction of a Cylindrical Tank with a Flexible Baseplate
Analytically predicted coupled natural frequencies, response functions, and transient responses are compared with measured values for a partially filled cylindrical tank subject to excitation...
Fluid Structure Interaction Analysis of a Concrete Suppression Chamber of Mark I Containment System
Recent studies have demonstrated that the interaction between a structure and fluid can have a significant influence on the response of the overall system when subjected to certain dynamic...
A Pseudo Response Spectrum Method for Mark I Loads
A pseudo base motion response spectrum method is developed to uniquely evaluate the periodic condensation oscillation and chugging drag loads that may occur on submerged structures within...
A Computer Integrated Engineering System for Nuclear Plant Design
The design, construction, and licensing of nuclear power facilities is a long and complicated process which can span a time period of over ten years. This tremendous lead time to plant...
Experimental Determination of Fluid-Coupling Coefficients in an Array of Hexagonal Prisms
The problem is related to the seismic analysis of fast breeder reactor cores, where the fluid trapped between the subassemblies is known to have a considerable influence on the core response....
Pipeline Hydraulic Transient and Leak Detection Analysis
Liquid and gas pipelines cannot be properly designed with consideration of steady flow analysis techniques alone due to the possibility of pipeline failure resulting from uncontrolled...
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