Seismic investigations of the HDR Safety Program. Summary report
Creators
- 1. Kernforschungszentrum Karlsruhe GmbH (Germany)
- 2. Fraunhofer-Institut fuer Betriebsfestigkeit (LBF), Darmstadt (Germany)
- 3. Argonne National Lab., IL (United States)
Description
The primary objective of the seismic investigations, performed at the HDR facility in Kahl/Main, FRG was to validate calculational methods for the seismic evaluation of nuclear-reactor systems, using experimental data from an actual nuclear plant. Using eccentric mass shaker excitation the HDR soil/structure system was tested to incipient failure, exhibiting highly nonlinear response and demonstrating that structures not seismically designed can sustain loads equivalent to a design basin earthquake (DBE). Load transmission from the structure to piping/equipment indicated significant response amplifications and shifts to higher frequencies, while the response of tanks/vessels depended mainly on their support conditions. The evaluation of various piping support configurations demonstrated that proper system design (for a given spectrum) rather than number of supports or system stiffness is important to limiting pipe greens. Piping at loads exceeding the DBE eightfold still had significant margins and failure is improbable inspite of multiple support failures. The mean value for pipe damping, even under extreme loads, was found to be about 4%. Comparison of linear and nonlinear computational results with piping response measurements showed that predictions have a wide scatter and do not necessarily yield conservative responses underpredicting, in particular, peak support forces. For the soil/structure system the quality of the predictions did not depend so much on the complexity of the modeling, but rather on whether the model captured the salient features and nonlinearities of the system
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as TI94017566; NTIS; GPO.Files
26030427.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 91 p.
- Report number
- NUREG/CR--6236
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26030427
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CALCULATION METHODS; CONCRETES; CRACKS; DYNAMIC LOADS; FAILURES; HDR REACTOR; MECHANICAL VIBRATIONS; PIPES; REACTOR SAFETY; RESPONSE FUNCTIONS; RESTRAINTS; SEISMIC EFFECTS; SOIL-STRUCTURE INTERACTIONS; STRESSES; SUPPORTS; TESTING
- Descriptors DEC
- BUILDING MATERIALS; BWR TYPE REACTORS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUNCTIONS; MATERIALS; MECHANICAL STRUCTURES; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- ANL--94/20.