Abstract
This paper describes the computational fluid dynamics (CFD) methodology to simulate the boiling flow in a typical Pressurized Water Reactor (PWR) 5 ⨯ 5 rod bundle. The method includes the Eulerian-Eulerian two-fluid model coupled with the improved wall heat partitioning model. The NUPEC PWR Subchannel and Bundle Test (PSBT) International Benchmark are used for validation. The simulated surface averaged void fraction agree well with the experimental data, which indicate the promising application of the present method for modeling the boiling flow in the fuel rod bundle. The main emphasis of current research has been given to the analysis of the phase distribution around and downstream the spacer grid, the effect of the spacer grid structure, including the mixing vanes, the springs and the dimples on the void fraction distribution is investigated. The findings can contribute to a better understanding of three dimensional flow boiling characteristics and can be used to assist in optimizing the spacer grid.
Kurzfassung
Dieser Beitrag beschreibt die Berechnung einer siedenden Strömung in einem typischen 5 ⨯ 5-Stabbündel eines Druckwasserreaktors (DWR) mit Hilfe eines Computational Fluid Dynamics Programms. Die Methode beinhaltet das Euler-Euler’sche Zwei-Fluid-Modell gekoppelt mit einem verbesserten Wandwärmeverteilungsmodell. Das Modell wird am NUPEC PWR Subchannel and Bundle Test (PSBT) International Benchmark validiert. Der Vergleich zeigt, dass das berechnete oberflächengemittelte Dampfvolumen gut mit den experimentellen Daten übereinstimmt. Dies weist auf eine vielversprechende Anwendung der vorliegenden Methode zur Modellierung der siedenden Strömung im Brennstabbündel hin. Der Schwerpunkt der aktuellen Forschung liegt auf der Analyse der Phasenverteilung um und hinter dem Spacergitter. Der Einfluss der Spacergitterstruktur, einschließlich der Mischflügel, der Federn und der Dimples auf die Hohlraumanteilsverteilung wird untersucht. Die Ergebnisse können zu einem besseren Verständnis des dreidimensionalen Strömungssiedens beitragen und als Hilfestellung für die Optimierung des Spacergitters dienen.
Acknowledgement
The support provided by OECD/NEA and JNES is gratefully acknowledged. The data used in this study is from the OECD/ PSBT benchmark of OECD/NEA and JNES.
References
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Articles in the same Issue
- Frontmatter
- The simulation research on the natural circulation operation characteristic of FNPP in rolling and inclined condition
- Establishment of analysis methodology of RADTRAD for Maanshan PWR ATWS
- Calendar of Events
- CFD simulation of subcooled boiling flow in PWR 5 ⨯ 5 rod bundle
- Effectiveness assessment of improvement measures in physical protection system monitoring center
- A study on accumulator analysis for the valve performance evaluation system of nuclear power plants
- Calculation studies of coated particles performance in sodium-cooled fast reactor
- Effect of using graphene/water based nanofluid on heat transfer in heat exchangers with rotating straight inner tube
- Radiation shielding properties of mortars containing heavyweight particles
- Improvement of the passive efficiency calibration of the segmented gamma scanner
- Investigation of level density parameter dependence for some 233U, 235U, 237U, 239U, 249Cf, 251Cf, 237Pu and 247Cm nuclei in neutron fission cross sections with the incident energy up to 20 MeV
- Establishment of analysis methodology for ionizing mattresses using RESRAD-BUILD code
- Editorial