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...
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...
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...
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...
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...
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,...
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