Seismic Qualification of Main Control Boards by Combined Mathematical Model and In-situ Modal Test
By adjusting the stiffness of the model, mode shapes and frequencies can be matched to those from the in-situ tests, thus giving a verified and representative model. With the verified...
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...
A Summary of the Seismic Qualification Utilities Group (SQUG) Program
In 1980, the Nuclear Regulatory Commission (NRC) designated Unresolved Safety Issue (USI) A-46 to address the seismic safety of equipment in operating nuclear power plants. In 1982, the...
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...
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...
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...
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...
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...
Return to search