Seismic design and qualification of cable trays in nuclear power plants
The seismic approach presented here is accomplished by a combination of analysis and experiment. The dynamic analysis concerns the anchor loads at the interconnection of support and
Revision 3A to, "Generic Implementation Procedure (GIP) for Seismic
Rigid-mounted conduit and cable trays are inherently very stable and subject to minimal seismic amplification. A detailed dead load design review of these systems provides ample margin for
Westinghouse AP1000 Design Control Document Rev. 19
This appendix provides the design criteria for seismic Category I cable trays and their supports. Seismic Category II cable trays and their supports are also designed utilizing the design criteria of this appendix.
A Method for Seismic Qualification of Cable Tray Systems in Nuclear
This paper presents an approach to seismically qualify cable tray systems in nuclear power plants. The approach allows the use of standard tray and support designs by giving realistic consideration to the
Seismic analysis and design of electrical cable trays and support
Most cable trays in nuclear power plants are classified as seismic category I components. Current safety requirements dictate that all such components be adequately designed in order to
Cable Trays
The seismic design of cable trays in nuclear power plants benefits from extensive investigations of their behavior and performance in real earthquakes and in tests.
Nuclear Cable Tray System Seismic Analysis Using Performance
In numerous tremor designing applications, it is regularly expected to decide the seismic requests of designs through a progression of nonlinear reaction history examinations for example by coordinating
Seismic Design and Qualification of Cable Trays in Nuclear Power Plants
Home Grey Literature Proceedings International Association for Structural Mechanics in Reactor Technology (IASMiRT) 1981 - SMiRT 6 - Paris, France Seismic Design and Qualification of Cable
Performance-Based Earthquake Engineering Methodology for Seismic
This study presents not only material and geometry frequently used for cable tray but also the formula to estimate the maximum cable load which can be installed within cable tray.
Seismic qualification of electrical cable trays for nuclear power
Abstract In a nuclear power plant cables supported on the cable trays may be related to safety functions, control systems, power input etc. Such cable trays must be capable of withstanding
Vogtle Electric Generating Plant (VEGP) Units 3 and 4 Updated
Institute of Electrical and Electronic Engineers (IEEE), Standard 344-1987, IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations
Performance-Based Earthquake Engineering Methodology for Seismic
Nuclear power plant safety-related cable tray support systems subjected to seismic loadings were originally understood and designed to behave as linear elastic systems.
V.C. Summer Nuclear Station, Units 2 and 3, Rev. 3 to Updated
Institute of Electrical and Electronic Engineers (IEEE), Standard 344-1987, IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations
Revision 3A to, "Generic Implementation Procedure (GIP) for Seismic
The seismic review guidelines contained in this section are applicable to steel and aluminum cable tray and conduit support systems at any elevation in a nuclear power plant, provided the Bounding
Shaking Table Tests of the Cable Tray System in Nuclear Power
Abstract Two series of shaking table tests were performed to investigate the seismic performance and damping ratio of the cable tray system in nuclear power plants. The required
Test-based approach to cable tray support system
Nuclear power plant safety-related cable tray support systems subjected to seismic loadings were originally understood and designed to behave as linear elastic systems. This
Performance-Based Earthquake Engineering Methodology for Seismic
12 power plant (NPP) such as the cable tray system, hazard curve and spectra were defined for two 13 hazard levels of the ground motions, namely, operation basis earthquake, and safe shutdown
PERFORMANCE-BASED EARTHQUAKE ENGINEERING METHODOLOGY FOR NUCLEAR CABLE
To carry out the PEER PBEE procedure for a components of the nuclear power plant (NPP) such as the cable tray system, hazard curve and spectra were defined for two hazard levels of the ground
Related Video Reference
This video was associated with the source search result. Verify technical details against current product documentation and project requirements.
This reference is intended for preliminary fiber and communications infrastructure research. Optical interface, fiber type, port or core capacity, electrical input and output, enclosure protection, cooling, installation limits and applicable standards must be verified for the specific project.