Response of Subsystems on Inelastic Structures
Preliminary analyses are performed to obtain insight into the seismic response of subsystems supported on simple structures that yield during severe earthquake ground motions. Current...
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 I?Overview and Need for Integrated Approach
In this paper, an ASCE working group on impact effects in nuclear plants updates the review of this technology contained in a five-year-old ASCE report. In Part I, an overview is given...
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...
Design for Whipping Pipe Impact on Reinforced Concrete Panels
This paper describes determination of local and overall effects on reinforced concrete panels due to whipping pipe impact in postulated pipe break events. Local damage includes the prediction...
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...
Low Velocity Impact Tests on Reinforced Concrete Panels
The results of low velocity impact tests on reinforced concrete panels are presented. These tests were conducted to investigate the behavior of reinforced concrete flexural elements subjected...
Behavior of an Operating Floor Subjected to Heavy Load Drops
A structural evaluation of the behavior of a Boiling Water Reactor operating floor subjected to postulated heavy load impact is presented relative to the evaluation of nuclear industry...
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...
Reliability Assessment of Indian Point Unit 3 Containment Structure Under Combined Loads
In the current design criteria, the load combinations specified for design of concrete containment structures are in the deterministic format. However, by applying the probability-based...
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...
Treatment of Design and Construction Errors in PRA
The risk estimates developed in a PRA should allow for potential design and construction errors. These errors generally modify the component responses and fragilities. Since most design...
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...
Desin Control for Nuclear Power Plant Modifications
Modifications to operating nuclar power plants which impact structural components must be performed in a manner that is consistent with the licensing basis and technical specifications...
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....
New Developments in Seismic Analysis of Primary and Secondary Systems
This paper presents recent advances made at NCSU in the seismic analysis of these systems. Algorithms are presented by which coupled mode shapes and frequencies can be evaluated without...
State-of-the-Art of Development of Floor Spectra
Floor spectra are used as seismic inputs for the design and qualification of subsystems and equipment. Until very recently, the time history analyses with single acceleration time history...
A Study of the Correlation of the Components of Instructure Motions During Earthquakes
Thirty-two buildings are selected that have all three components of motion recorded in the basement, midheight and top of the structure. The correlation coefficients of these motions,...
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