Heat transfer to the building structures of the Ignalina NPP accident localisation system
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E. Babilas
Abstract
The performed thermal-hydraulic analysis of the Accident Localisation System (ALS) has shown, that in the case of a Maximum Design Basis Accident (MDBA), in the long term, a significant amount of energy (∼40%) is transferred to the building structures. Therefore, special attention should be paid to the correct simulation of the building structures and heat transfer processes. Free convection, forced convection, condensation and conductivity are the phenomena, which are connected with the heat transfer to the building structures and should be investigated. In this paper, the heat transfer models available in the COCOSYS code, which is applied for the analysis, are discussed. The influence of the heat transfer models on the behaviour of thermal-hydraulic parameters in ALS compartments during MDBA is investigated.
Kurzfassung
Die durchgeführte thermohydraulische Analyse des Confinements hat gezeigt, dass im Verlauf eines maximalen Auslegungsstörfalls (DBA) ein bedeutender Energiebetrag (∼40%) auf die Baustrukturen übertragen wird. Deshalb sollte die Modellierung von Baustrukturen und von Wärmeübertragungsprozessen besonders sorgfältig betrachtet werden. Natur- und Zwangskonvektion, Kondensation und Leitfähigkeit sind die Phänomene, die mit der Wärmeübertragung auf die Baustrukturen verbunden sind und untersucht werden sollten. Im vorliegenden Beitrag werden die Wärmeübertragungsmodelle des COCOSYS-Codes diskutiert. Der Einfluss der Wärmeübertragungsmodelle auf das Verhalten von thermohydraulischen Parametern in Confinement-Räumen während eines Auslegungsstörfalls (DBA) wird untersucht.
References
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© 2010, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- European clearinghouse on nuclear power plants operational experience feedback
- Investigation on primary side oriented accident management measures in a hypothetical station blackout scenario for a VVER-1000 pressurized water reactor
- Heat transfer to the building structures of the Ignalina NPP accident localisation system
- Algorithmic determination of fuel rod cladding burst time at elevated temperatures
- Development of a decommissioning strategy for the MR research reactor
- Neutron transmutation doping conceptual design
- Design optimization of shell-and-tube heat exchangers using single objective and multiobjective particle swarm optimization
- Chebyshev polynomials expansion method for solving the one-dimensional transport equation in spherical geometry
- Heuristic geometric “eigenvalue universality” in a one-dimensional neutron transport problem with anisotropic scattering
- An analytical solution for the one-dimensional time-dependent SN transport equation for bounded and unbounded domains in cartesian geometry
- Accurate critical slab calculations for various degrees of anisotropy and for different reflection coefficients
- Technical Notes/Technische Mitteilungen
- The boundary problem in the 1D-CANDLE burn-up reactor
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- European clearinghouse on nuclear power plants operational experience feedback
- Investigation on primary side oriented accident management measures in a hypothetical station blackout scenario for a VVER-1000 pressurized water reactor
- Heat transfer to the building structures of the Ignalina NPP accident localisation system
- Algorithmic determination of fuel rod cladding burst time at elevated temperatures
- Development of a decommissioning strategy for the MR research reactor
- Neutron transmutation doping conceptual design
- Design optimization of shell-and-tube heat exchangers using single objective and multiobjective particle swarm optimization
- Chebyshev polynomials expansion method for solving the one-dimensional transport equation in spherical geometry
- Heuristic geometric “eigenvalue universality” in a one-dimensional neutron transport problem with anisotropic scattering
- An analytical solution for the one-dimensional time-dependent SN transport equation for bounded and unbounded domains in cartesian geometry
- Accurate critical slab calculations for various degrees of anisotropy and for different reflection coefficients
- Technical Notes/Technische Mitteilungen
- The boundary problem in the 1D-CANDLE burn-up reactor
