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...
Pipe Impact on Concrete Slabs
A series of pipe impact on concrete slab tests have been performed at the CEA's Cadarache Laboratory using the AQUITAINE II facility. The testing program was jointly sponsored...
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...
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...
Seismic Evaluation of Reinforced Masonry Walls
Masonry walls in operating nuclear plants are in many cases found to be overstressed in terms of allowable stresses when evaluated using current seismic design criteria. However, experimental...
Seismic Capacities of Masonry Walls at the Big Rock Point Nuclear Generating Plant
An evaluation to determine the ability of selected concrete block walls in the vicinity of essential equipment to withstand seismic excitation was conducted. The seismic input to the walls...
The Use of Joint Reinforcement in Qualifying Masonry Walls in Nuclear Power Plants
Wire joint reinforcement has been traditionally used in block masonry walls for crack control and to provide continuity for multiple wythe walls. In a number of nuclear power plants, vertically...
Probabilistic Seismic Analysis of a Nuclear Power Plant Steel Containment
Concern for the safety of nuclear power plants has motivated efforts to determine the statistical characteristics of the seismic resistance of steel containments under various types of...
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,...
Tension Tests of Containment Wall Isolated Liner Plates
Two tests were conducted using an approximate 2:1 ratio of hoop to meridional load. This simple load ratio is a gross approximation of the liner plate loading in a containment subjected...
Preliminary Analysis of Large Penetration Enclosures for Containment Vessels Subject to Beyond Design Basis Loadings
Numerical simulations of the macro-deformations of the sealing surfaces (gasketed junctures) of a PWR steel containment vessel's equipment hatch subjected to accident loadings...
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,...
Modeling Techniques for Seismic Analysis of Supported Systems
An automated seismic qualification process is presented which integrates the modeling and evaluation aspects of supported system design. Emphasis is placed on baseplate and joint design....
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...
Vibration Isolation of Cable Tray Hangers
Analytical and experimental investigations have been performed to partially evaluate the feasibility of using much more flexible support systems than those presently used to support electrical...
Piping Analysis: A Flexibility Approach
Design for the vertical and horizontal accelerations associated with a seismic event coupled with low allowable loads on equipment are two primary contributors to the current situation....
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