Research on multi-scale simulation model for single-phase water pipe networks
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J.-L. Sun
Abstract
Fluid transients occur mainly during fluid transfer in the networked pipe systems in nuclear power plants. Research on pipe network simulation is presented in literature. However, there are still some open technical gaps. In this paper, to satisfy the different time step requirements in different stages of nuclear power plant operation, and to improve the accuracy of simulation results, a multi-scale simulation model of single-phase water pipe networks is proposed. Therefore, the pipe networks are divided into control nodes and flow lines in a complete simulation map. The multi-scale simulation is obtained through the combination of simplified equations, time step selection and refined nodes. The accuracy and stability of the simulator are verified by modeling the feed water system of the Chinese experimental fast reactor. In addition, the output is compared with output of the commercial software, Jtopmeret. As a conclusion, the new model calculates results for this feed water system with a higher accuracy under dynamic operations which consistent with theoretical analysis.
Kurzfassung
Transienten treten vor allem während der Strömung von Flüssigkeiten in den Rohrleitungssystemen in Kernkraftwerken auf. Die Forschung zur Simulation dieser Rohrleitungssyteme ist in der Literatur vorgestellt. Allerdings gibt es noch einige offene Fragestellungen. Um die unterschiedlichen Zeitschrittanforderungen in den verschiedenen Phasen des Kernkraftwerksbetriebs zu erfüllen und die Genauigkeit der Simulationsergebnisse zu verbessern, wird in diesem Beitrag ein mehrstufiges Simulationsmodell für einphasige Wasserrohrnetze vorgeschlagen. Dabei werden die Rohrnetze vollständig in Kontrollknoten und Strömungslinien unterteilt. Die Multiskalensimulation wird durch die Kombination von vereinfachten Gleichungen, Zeitschrittauswahl und verfeinerten Knoten erreicht. Die Genauigkeit und Stabilität des Simulators wird durch die Modellierung des Speisewassersystems des chinesischen experimentellen schnellen Reaktors überprüft. Darüber hinaus werden die Ergebnisse mit den Ergebnissen der Rechnungen mit der kommerziellen Software Jtopmeret verglichen. Als Fazit berechnet das neue Modell die Ergebnisse für dieses Speisewassersystem mit einer höheren Genauigkeit unter dynamischen Bedingungen, die mit der theoretischen Analyse übereinstimmen.
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© 2019, Carl Hanser Verlag, München
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- Experimental study on penetration characteristic of submerged steam jet in quiescent water
- Research on multi-scale simulation model for single-phase water pipe networks
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Artikel in diesem Heft
- Technical Contributions/Fachbeiträge
- The simulation and study of ELAP event with URG and FLEX mitigation strategies for PWR by using TRACE code
- Experimental study on penetration characteristic of submerged steam jet in quiescent water
- Research on multi-scale simulation model for single-phase water pipe networks
- Determination of radiological source term of CHASHMA-1 NPP during LOCA
- Assessment of the health damage costs of radionuclides releases from Muğla provinces lignite-fired power plants
- Natural radioactive risk assessment in top soil and possible health effect in Minim and Martap villages, Cameroon: using radioactive risk index and statistical analysis
- ATWS severe accident analysis in the loss of flow scenario using the MELCOR code in Bushehr nuclear Power Plant
- Evaluation of spent fuel transport cask from the radiological point of view
