Response of HDR-VKL piping system to seismic test excitations: Comparison of analytical predictions and test measurements
Description
As part of the earthquake investigations at the HDR (Heissdampfreaktor) Test Facility in Kahl/Main, FRG, simulated seismic tests (SHAM) were performed during April--May 1988 on the VKL (Versuchskreislauf) piping system. The purpose of these experiments was to study the behavior of piping subjected to a range of seismic excitation levels including those that exceed design levels manifold and 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 used to validate analysis methods. Detailed reports on the SHAM experiments are given elsewhere. The objective of this document is to evaluate a subsystem analysis module of the SMACS code. This module is a linear finite-element based program capable of calculating the response of nuclear power plant subsystems subjected to independent multiple-acceleration input excitation. The evaluation is based on a comparison of computational results of simulation of SHAM tests with corresponding test measurements
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A03/MF A01 - OSTI as DE89009782; US Govt. Printing Office Dep.Files
20079207.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 13 p.
- Report number
- CONF-890855--9
Conference
- Title
- 10. international conference on Structural Mechanics in Reactor Technology (SMIRT).
- Dates
- 14-18 Aug 1989.
- Place
- Anaheim, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20079207
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- EXPERIMENTAL DATA; FAILURES; FINITE ELEMENT METHOD; HDR REACTOR; PIPES; REACTOR SAFETY; RESPONSE FUNCTIONS; S CODES; SEISMIC EFFECTS; SUPPORTS; TESTING
- Descriptors DEC
- BWR TYPE REACTORS; COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUNCTIONS; INFORMATION; MECHANICAL STRUCTURES; NUMERICAL DATA; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract DOE W-31109-ENG-38