ATWS severe accident analysis in the loss of flow scenario using the MELCOR code in Bushehr nuclear Power Plant
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F. Janbazi
Abstract
The analysis of accident scenarios in a nuclear power plant and consequently a review of the proper functioning of safety systems is very importance. In this paper, an analysis of a anticipated transient without scram has been done in the Loss of flow scenario with modeling the VVER-1000 reactor of Bushehr by MELCOR1.8.6 code. The chronological sequence of the different steps and the history of the parameters under this accident calculated with the code are evaluated. Parameters such as temperature and pressure changes in the primary and secondary circuit, temperature changes of fuel and fuel clad are calculated as well as a comparison with the melting temperature. Also, the rate of hydrogen production and pouring molten material into the reactor cavity is calculated. This information is very useful for managing the ATWS accident and controlling the reactor. Also, this results to assess Bushehr nuclear power plant. The results show that thermodynamic parameters of pressure and temperature passes the limit without any accident management.
Kurzfassung
Die Analyse von Unfallszenarien in einem Kernkraftwerk und damit die Überprüfung der Funktionsfähigkeit von Sicherheitssystemen ist sehr wichtig. In diesem Beitrag wurde eine Analyse eines ATWS während eines Loss of Flow-Szenario durchgeführt. Dazu wurde der VVER-1000 Reaktor von Bushehr mit dem Programm MELCOR1.8.6 modelliert und das Szenario gerechnet. Die chronologische Abfolge der verschiedenen Schritte und der Verlauf der berechneten Parameter während dieses Unfalls werden vorgestellt. Es werden Temperatur- und Druckänderungen im Primär- und Sekundärkreislauf, Temperaturänderungen des Brennstoffs sowie ein Vergleich mit der Schmelztemperatur bestimmt. Außerdem wird die Geschwindigkeit der Wasserstofferzeugung und des Fließens von geschmolzenem Material in den Reaktorhohlraum berechnet. Diese Informationen sind sehr nützlich für das Management des ATWS-Unfalls und die Steuerung des Reaktors. Die Ergebnisse zeigen, dass die thermodynamischen Parameter von Druck und Temperatur die jeweiligen Grenzwerte ohne Unfallmanagement überschreiten.
References
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© 2019, Carl Hanser Verlag, München
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Articles in the same Issue
- 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
