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...
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,...
Major Considerations in Scale Modeling of Reinforced Concrete Containment Structures
Reinforced concrete containment structures pose unique modeling problems, especially when leakage integrity is of interest. This paper presents a general discussion of modeling considerations...
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...
Evaluation of the Ultimate Pressure Capacity of Rectangular HVAC Ducts for Nuclear Power Plants
Structural design criteria are presently based on the AISI Code which limits the duct panel width-to-thickness ratio to a maximum of 500 and the maximum height-to-thickness ratio to 200,...
Analytical Solution of Cable Tray Hanger 3D Structural Interaction under Seismic Loading
Structural design of cable tray hangers is controlled by the Nuclear Regulatory Commission's stringent requirements of seismic analysis. A finite element space frame model...
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