Reduction of operational vibration and seismic design of the feedwater piping system of the VVER-440/213 at PAKS
Creators
- 1. Nuclear Power Plant Paks Ltd. (Hungary)
- 2. Siemens AG, Erlangen (Germany). Power Generation Group
Description
The feed-water piping system in unit 3 of the nuclear power plant in Parks was suffering strong operational vibration. To reduce this vibration and also ti increase the seismic safety, the piping was analysed and optimised. In order to solve the problem measuring and calculations were combined efficiently: Vibrations measured were used both for a first evaluation of damaging potential of the operational vibrations as well as for the optimisation of a calculation model. The reduction of the operational vibrations and the improvement of the strength during earthquake were achieved by means of viscous dampers, the parameters, the parameters of which were determined by a strategy of maximizing the energy dissipation in the relevant frequency range. The calculation showed a significant reduction of the operational vibrations for the system with dampers. The vibration amplitudes are reduced 1/10 of the original values. The measurements designed have in the meantime been partially carried out and the measurements confirm the favourable prognosis of the calculation. (author). 4 refs., 6 figs
Additional details
Publishing Information
- Publisher
- Editora de Universidade Federal do Rio Grande do Sul.
- Imprint Place
- Porto Alegre, RS (Brazil)
- ISBN
- 85-7025-350-8
- Imprint Title
- Transactions of the 13. International Conference on Structural Mechanics in Reactor Technology. v. 2
- Imprint Pagination
- 897 p.
- Journal Page Range
- p. 329-334.
Conference
- Title
- 13. International Conference on Structural Mechanics in Reactor Technology.
- Dates
- 13-18 Aug 1995.
- Place
- Porto Alegre, RS (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 28001750
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DYNAMIC LOADS; FEEDWATER; FINITE ELEMENT METHOD; MECHANICAL VIBRATIONS; OSCILLATIONS; PIPES; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; REACTOR TECHNOLOGY; REACTORS; SEISMIC EFFECTS; STRESS ANALYSIS; STRESSES; WWER TYPE REACTORS
- Descriptors DEC
- CALCULATION METHODS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; NUMERICAL SOLUTION; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; SAFETY; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Conference organized by the International Association for Structural Mechanics in Reactor Technology and Universidade Federal do Rio Grande do Sul.