Methods and algorithms of calculations of quality factor of a stream of the coolant are developed. Quantitative estimations of a range of frequency of vibration - acoustical resonance between the coolant flowing through the reactor core and fuel assembly vibration in the NPP with WWER-1000 are provided. The experimental substantiation of sharp increase of intensity of vibrations at occurrence of vibration - acoustical resonance is received. Destructions at Fukushima Daiichi NPP caused by earthquake have shown that design level of seismic influences on the equipment has been exceeded. The accident demonstrated the need for stricter regulations to ensure the seismic resistance of NPP and the need to develop and implement additional anti-seismic procedures in the course of their operation. The results of the analysis of the causes of the destruction of the cooling systems of nuclear reactors from earthquakes are presented. Results should serve as a basis for developing more realistic recommendations to assess the expected level of seismic effects on the NPP.
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2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference
July 30–August 3, 2012
Anaheim, California, USA
Conference Sponsors:
- Nuclear Engineering Division
- Power Division
ISBN:
978-0-7918-4495-3
PROCEEDINGS PAPER
The Reasons of Rupture of Systems of Cooling of the Reactor as a Result of Earthquake
Konstantin Proskuryakov
Konstantin Proskuryakov
Moscow Power Engineering Institute (National Research University), Moscow, Russia
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Konstantin Proskuryakov
Moscow Power Engineering Institute (National Research University), Moscow, Russia
Paper No:
ICONE20-POWER2012-55283, pp. 283-288; 6 pages
Published Online:
October 30, 2013
Citation
Proskuryakov, K. "The Reasons of Rupture of Systems of Cooling of the Reactor as a Result of Earthquake." Proceedings of the 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance. Anaheim, California, USA. July 30–August 3, 2012. pp. 283-288. ASME. https://doi.org/10.1115/ICONE20-POWER2012-55283
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