A combined testing and analysis approach to nuclear equipment qualification
Creators
- 1. Structural Dynamics Lab., National Technical Systems, Fullerton, CA
Description
This paper describes the procedures and methods used to determine if a safety-related HVAC control panel for a nuclear power plant meets both seismic and hydrodynamic load requirements. The finite element analysis of the panel was performed using the Engineering Analysis Language (EAL) program. Topics considered include seismic stress analysis, the modal test procedure (fixturing, resonance survey, excitation position survey, excitation position selection, damping survey), the transmissibility test procedure, and the instrument response spectra. The results indicate that the combined testing and analysis method using digital signal processing/modal testing and finite element techniques is a viable approach to the seismic qualification of Class 1E equipment. It is shown that low-level excitation tests and corresponding damping studies can justify the use of required response spectra with higher damping values
Additional details
Publishing Information
- Journal Title
- Proc. Am. Power Conf.
- Journal Volume
- 45
- Series
- Proc. Am. Power Conf.
- Journal Page Range
- 788-798
- ISSN
- 0097-2126
Conference
- Title
- American Power conference.
- Dates
- 18-20 Apr 1983.
- Place
- Chicago, IL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16010880
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AIR CONDITIONING; COMPUTER CALCULATIONS; COMPUTER CODES; CONTROL EQUIPMENT; DAMPING; DATA PROCESSING; DIGITAL SYSTEMS; E CODES; ELECTRICAL EQUIPMENT; EXCITATION; FINITE ELEMENT METHOD; HYDRODYNAMICS; NUCLEAR POWER PLANTS; REACTOR SAFETY; RESONANCE; SEISMIC EFFECTS; SIGNALS; SPACE HEATING; STRESS ANALYSIS; TESTING; VENTILATION
- Descriptors DEC
- ENERGY-LEVEL TRANSITIONS; EQUIPMENT; FLUID MECHANICS; HEATING; MECHANICS; NUCLEAR FACILITIES; NUMERICAL SOLUTION; POWER PLANTS; SAFETY; THERMAL POWER PLANTS
Optional Information
- Secondary number(s)
- CONF-830446--.