Published 1996
| Version v1
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Evaluation of potential hazard for operating WWER control rods under seismic excitation
Description
The experimental and computer analyses of the 1/4 scale Control Rod Drive System (CRDS) model of WWER-440 reactor has been carried out. The experimental study has been undertaken on CVS 20 tons capacity shaking table with modeling operability of CRDS during earthquake and operational vibration. A special PC computer program has been developed for evaluation of CRDS seismic and vibration margins. The program enables estimation of different nonlinear effects in bearings and gaps of CRDS including shocks and friction that highly influence on dynamic capacity of CRDS. The results of these investigations are presented in this paper
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Additional details
Publishing Information
- Imprint Title
- Co-ordinated research programme on benchmark study for the seismic analysis and testing of WWER-type nuclear power plants. V. 4D. Paks NPP: Analysis and testing. Working material
- Imprint Pagination
- [278 p.]
- Journal Page Range
- [34 p.]
- Report number
- INIS-XA--196
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 30052383
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CALCULATIONS; CONTROL ELEMENTS; CONTROL ROD DRIVES; DYNAMIC LOADS; IMPACT SHOCK; MECHANICAL VIBRATIONS; OSCILLATION MODES; WWER-3 REACTOR
- Descriptors DEC
- ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- 2 refs, 23 figs