3D thermal hydraulic simulation of the hot channel of a typical material testing reactor under normal operation conditions
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S. El-Din El-Morshedy
Abstract
The hot channel in a typical Material Testing Reactor (MTR) is subjected to 3D simulation. Because of the existence of similarity planes, only a quarter of the hot channel including meat thickness, clad, and coolant channel is considered for CFD analysis using the FLUENT code. For the simulation, steady state normal operation regime at the reactor nominal power is assumed. In order to build confidence in our modeling approach, the results obtained in this work are compared with those obtained from the one-dimensional simulation code, MTRTHA. That is, modified variables were generated in order to match those obtained by MTRTHA and to allow comparisons. Quite good agreement is generally observed, however, the maximum clad surface temperature predicted by the 3D calculations, located at the clad mid-width, is higher than the 1D prediction by about 8°C but still below the onset of subcooled boiling by adequate safety margin. The results show quite interesting 3D patterns in both the flow field and the heat transfer. Temperature profiles, velocity profiles and contours are all presented to highlight the essential 3D features of this system.
Kurzfassung
Der Heißkanal in einem typischen Materialprüfungsreaktor (MTR) wurde einer 3D Simulation unterzogen. Wegen des Vorhandenseins von ähnlicher Ebenen wird nur ein Viertel des Heißkanals inklusive Brennstoffgehalt, Hülle und Kühlkanal für die CFD Analyse mit Hilfe des FLUENT Code betrachtet. Für die Simulation werden normale Betriebsbedingungen im stationären Zustand bei nominaler Leistung des Reaktors angenommen. Zur Vertrauensbildung in Bezug auf den Modellansatz wurden die Ergebnisse mit denjenigen Ergebnissen verglichen, die mit Hilfe des eindimensionalen Simulationscodes MTRTHA erhalten wurden. Bei dieser Simulation werden veränderte Variablen erzeugt und an die von MTRTHA erhaltenen Werte angepasst um so Vergleiche zu erlauben. Generell wird eine gute Übereinstimmung beobachtet. Die durch die 3D Berechnungen vorhergesagte maximale Hüllentemperatur in der Mitte der Hülle ist um 8°C höher als die durch die 1D Berechnung vorhergesagte Temperatur, aber immer noch vor dem Einsetzen unterkühlten Siedens durch geeignete Sicherheitsspannen. Die Ergebnisse zeigen interessante 3D Muster, sowohl im Strömungsfeld als auch beim Wärmetransfer. Temperaturprofile, Geschwindigkeitsprofile und Konturen werden präsentiert, um die wesentlichen 3D Merkmale dieses Systems hervorzuheben.
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© 2010, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Integrated online condition monitoring system for nuclear power plants
- Performance analysis of 233U for fixed bed nuclear reactors
- 3D thermal hydraulic simulation of the hot channel of a typical material testing reactor under normal operation conditions
- Analysis of the processes in the target cooling system of the W7-X fusion experiment
- Nuclear model calculation on charged particle induced reactions to produce 85Sr for diagnostic and endotherapy
- Neutronic and burn-up calculations of heterogeneous Thorium/Uranium fuel in pressurized water reactors
- Research on pitting corrosion of steam generator heat transfer tubes based on acoustic emission
- Application of the Chebyshev polynomial (TN and UN) approximation to reflected slab geometry in the neutron transport equation and computation of critical half thicknesses
- UN approximation to critical slab problem for one-speed neutrons with isotropic, forward and backward scattering
- The albedo problem for pure-quadratic anisotropic scattering with İnönü scattering
- Technical Notes/Technische Mitteilungen
- Targetry of Y2O3 on a copper substrate for the non-carrier-added 89Zr production via 89Y(p, n)89Zr reaction
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Integrated online condition monitoring system for nuclear power plants
- Performance analysis of 233U for fixed bed nuclear reactors
- 3D thermal hydraulic simulation of the hot channel of a typical material testing reactor under normal operation conditions
- Analysis of the processes in the target cooling system of the W7-X fusion experiment
- Nuclear model calculation on charged particle induced reactions to produce 85Sr for diagnostic and endotherapy
- Neutronic and burn-up calculations of heterogeneous Thorium/Uranium fuel in pressurized water reactors
- Research on pitting corrosion of steam generator heat transfer tubes based on acoustic emission
- Application of the Chebyshev polynomial (TN and UN) approximation to reflected slab geometry in the neutron transport equation and computation of critical half thicknesses
- UN approximation to critical slab problem for one-speed neutrons with isotropic, forward and backward scattering
- The albedo problem for pure-quadratic anisotropic scattering with İnönü scattering
- Technical Notes/Technische Mitteilungen
- Targetry of Y2O3 on a copper substrate for the non-carrier-added 89Zr production via 89Y(p, n)89Zr reaction
