Analytical simulation of seismic testing of VKL (Versuchskreislauf) piping system at the HDR (Heissdampfreaktor) Test Facility
Conference
·
OSTI ID:7038148
Dynamic tests with simulated earthquake excitation (SHAM) were performed during April--May 1988 on the VKL (Versuchskreislauf) piping system at the HDR (Heissdampfreaktor) Test Facility in Kahl/Main, Federal Republic of Germany. The major objectives of these test were to study the behavior of a full-scale in-plant piping system subjected to a range of seismic excitation levels, from design levels to those that exceed design levels manifold and those that might induce failure of pipe supports or plasticity in the pipe runs, and to establish seismic margins for piping and pipe supports. Data obtained in the tests are also being used to validate analytical method for piping response calculation. Detailed reports on the SHAM experiments are given elsewhere. The paper describes an effort to evaluate the subsystem analysis module of the SMACS code using some of the SHAM test data. The SMACS modules a linear finite-element program, derived from the SAP4 code and capable of calculating the response of nuclear power plant subsystems subjected to multiple, independent acceleration excitation. The evaluation is based on a comparison of computational results of simulation of SHAM test with corresponding test measurements. 4 refs., 7 figs., 2 tabs.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- NRC
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 7038148
- Report Number(s):
- CONF-900617-2; ON: DE90005660
- Country of Publication:
- United States
- Language:
- English
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99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACTUATORS
BWR TYPE REACTORS
COMPARATIVE EVALUATIONS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINERS
DATA PROCESSING
DESIGN
DYNAMICS
EARTHQUAKES
EIGENFUNCTIONS
ENRICHED URANIUM REACTORS
EUROPE
EXPERIMENTAL REACTORS
FEDERAL REPUBLIC OF GERMANY
FUNCTIONS
HDR REACTOR
MATHEMATICAL MODELS
MECHANICS
PERFORMANCE TESTING
PIPES
PROCESSING
REACTOR COMPONENTS
REACTOR SAFETY
REACTOR VESSELS
REACTORS
RECOMMENDATIONS
RESEARCH AND TEST REACTORS
S CODES
SAFETY
SEISMIC EFFECTS
SEISMIC EVENTS
SIMULATION
STATISTICAL MODELS
STRESS ANALYSIS
TESTING
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTERN EUROPE