High level seismic/vibrational tests at the HDR - An overview
Creators
- 1. Argonne National Lab., IL (United States)
- 2. Kernforschungszentrum Karlsruhe (Germany)
- 3. Fachhochschule Giessen, Friedberg (Germany)
Description
As part of the Phase 2 testing at the HDR Test Facility in Kahl/Main, Federal Republic of Germany two series of high-level seismic/vibrational experiments were performed. In the first of these (SHAG) a coast-down shaker, mounted on the reactor operating floor and capable of generating 1,000 tonnes of force, was used to investigate full-scale structural response, soil-structure interaction (SSI), and piping/equipment response at load levels equivalent to those of a design basis earthquake. The HDR soil/structure system was tested to incipient failure exhibiting highly nonlinear response. In the load transmission from structure to piping/equipment significant response amplifications and shifts to higher frequencies occurred. The performance of various pipe support configurations was evaluated. This latter effort was continued in the second series of tests (SHAM), in which an in-plant piping system was investigated at simulated seismic loads (generated by two servo-hydraulic actuators each capable of generating 40 tonnes of force), that exceeded design levels manifold and resulted in considerable pipe plastification and failure of some supports (snubbers). The evaluation of six different support configurations demonstrated that proper system design (for a given spectrum) rather than number of supports or system stiffness is essential to limiting pipe stresses. Pipe strains at loads exceeding the design level eightfold were still tolerable, indicating that pipe failure even under extreme seismic loads is unlikely in spite of multiple support failures. Conservatively, an excess capacity (margin) of at least four was estimated for the piping system, and the pipe damping was found to be 4%
Additional details
Publishing Information
- Imprint Title
- Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting. Volume 3, Structural engineering; Advanced reactor research; Advanced passive reactors; Human factors research; Human factors issues related to advanced passive LWRs; Thermal hydraulics; Earth sciences
- Imprint Pagination
- 542 p.
- Journal Page Range
- p. 59-90.
- Report number
- NUREG/CP--0119-Vol.3
Conference
- Title
- 19. Nuclear Regulatory Commission (NRC) water reactor safety information meeting.
- Dates
- 28-30 Oct 1991.
- Place
- Bethesda, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24027140
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AMPLIFICATION; BENDING; BWR TYPE REACTORS; CONTAINMENT BUILDINGS; DAMPING; DYNAMIC LOADS; EARTHQUAKES; GROUND MOTION; HYSTERESIS; KERNFORSCHUNGSZENTRUM KARLSRUH; MATHEMATICAL MODELS; MECHANICAL STRUCTURES; NONLINEAR PROBLEMS; PIPES; PWR TYPE REACTORS; REACTOR OPERATION; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; REACTOR SHUTDOWN; RESPONSE FUNCTIONS; SEISMIC EFFECTS; SHOCK ABSORBERS; SOIL-STRUCTURE INTERACTIONS; SUPPORTS; TEST FACILITIES; US NRC; VERIFICATION
- Descriptors DEC
- BUILDINGS; CONTAINMENT; DEFORMATION; ENRICHED URANIUM REACTORS; FUNCTIONS; GERMAN FR ORGANIZATIONS; MOTION; NATIONAL ORGANIZATIONS; OPERATION; POWER REACTORS; REACTORS; SAFETY; SEISMIC EVENTS; SHUTDOWN; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-911079--Vol.3.