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...
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...
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 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...
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...
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...
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...
Integrated Testing and Analysis
This paper represents a new approach which greatly streamlines the entire process. In those cases where finite element modeling is used without test verification, the procedure consists...
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...
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,...
Strength and Stiffness Characteristics of Steel Ladder-Type Cable Trays
Ladder-type cable trays identical with the as-built are generally tested to establish their strength and stiffness characteristics. Test data for systems in operating plants, however,...
Return to search