Calculation of moderator circulation in IPHWR using a porosity approach
-
P. Goyal
Abstract
In the present configuration of the calandria for the 700 MWe Kakrapara Nuclear Power Plant, moderator inlet diffusers are directed upwards and the outlet is from the bottom of the calandria. Moderator circulation patterns and temperature distribution needs to be predicted to ensure adequate cooling margin for all channels. This study consists of two steps: at first, an optimized calculation scheme is obtained by comparison of the predicted results with the experimental data and by evaluating the fluid flow and temperature distribution. Then, in the second step, the analysis for the real 700 MWe IPHWR moderator under normal operating conditions has been performed with the optimized scheme. The present paper describes the methodology used for predicting the circulation pattern and temperature distribution in the moderator during normal operation using CFD code CFD-ACE+. The matrix of the calandria tubes in the core region is simplified to a porous media in which the momentum resistance model is used for pressure loss. The buoyancy effects due to internal heating and jet momentum effects through inlet nozzles have been considered in the analysis. The results show that the maximum temperature observed in the calandria is within the design limits during normal operation.
Kurzfassung
In der derzeitigen Konfiguration des Calandriabehälters des 700 MWe Kakrapara Kernkraftwerks sind die Moderator-Einlass-Diffusoren nach oben gerichtet und der Auslass ist am Boden der Calandria. Das Moderatorströmungsmuster und die Temperaturverteilung muss vorausberechnet werden um eine geeignete Sicherheitsspanne für die Kühlung aller Kanäle sicher zu stellen. Die vorliegende Arbeit umfasst zwei Schritte: zuerst erhält man ein optimiertes Berechnungsschema durch Vergleich vorhergesagter Ergebnisse mit experimentellen Daten und durch Auswertung der Flüssigkeitsströmung und der Temperaturverteilung. Dann wird in einem zweiten Schritt mit dem optimierten Berechnungsschema die Analyse für den tatsächlichen Moderator des 700 MWe Indischen Druckwasserreaktors (IPHWR) unter normalen Betriebsbedingungen durchgeführt. Die vorliegende Arbeit beschreibt die Methode für die Berechnung des Strömungsmusters und der Temperaturverteilung im Moderator unter normalen Betriebsbedingungen unter Verwendung des Rechencodes CFD-ACE+. Die Matrix der Calandriaröhren in der Kernregion wird vereinfacht als poröses Medium dargestellt, in dem das Impulswiderstandsmodell zur Berechnung des Druckverlustes verwendet wird. Der Buoyancy-Effekt aufgrund interner Wärmeeffekte durch die Einlaufdüsen wurde bei der Analyse berücksichtigt. Die Ergebnisse zeigen, dass die maximale, in der Calandria beobachtete Temperatur innerhalb der Auslegungsgrenzen für den normalen Betrieb liegt.
References
1 Design Manual on Moderator main Circulation and Adjuster Rods Cooling System Process and Instrumentation, DM No. KAIGA-3 & 4/DM/32000/01Search in Google Scholar
2 Quraishi, S.: A study of combined forced and natural convection flow using an analytical indicator flow visualization technique. 3rd International symposium flow visualization, Ann Arbor, Michigan (1983)Search in Google Scholar
3 Koroyannakis, D.; Hepworth, R. D.; Hendrie, G.: An Experimental Study of Combined Natural and Forced Convection Flow in a Cylindrical Tank. AECL Report. TDVI-382, 1983Search in Google Scholar
4 Carlucci, L. N.; Cheung, I.: The effects of Symmetric/Asymmetric Boundary Conditions on the Flow of an internally heated fluid. Numer. Methods PDE, 2, 47 (1986)10.1002/num.1690020105Search in Google Scholar
5 Huget, R. G.; Szymanski, J. K.; Midvidy, W. I.: Status of physical and numerical modeling of CANDU moderator circulation. Proceedings of 10th Annual conference Canadian Nuclear Society, Ottawa, June 4–7, 1989Search in Google Scholar
6 Huget, R. G.; Szymanski, J. K.; Midvidy, W. I.: Experimental and Numerical modeling of combined forced and free convection in a complex geometry with internal heat generation. Proceedings of 9th International Heat Transfer Conference, vol. 3, p. 327 (1990)10.1615/IHTC9.2620Search in Google Scholar
7 Huget, R. G.; Szymanski, J. K.; Galpin, P. F.; Midvidy, W. I.: MODTRUC-CLAS: An efficient code for analyses of moderator circulation in CANDU Reactors. 3rd International conference of Simulation Methods in nuclear engineering, Montreal, Canada, April 18–20, 1990Search in Google Scholar
8 Fath, H. E. S.; Hussein, M. A.: Moderator circulation in CANDU reactors: an alternative approach for the tube matrix simulation. Nuclear Technology88 (1989) 307–18Search in Google Scholar
9 Yoon, C.; Rhee, B. W.; Min, B.-J.: Development and validation of the 3-D CFD model for CANDU-6 moderator temperature predictions. Nuclear Technology148 (2004) 259–267Search in Google Scholar
10 ManwoongKim; Seon-OhYu; Hho-JungKim: Analyses on fluid flow and heat transfer inside Calandria vessel of CANDU-6 using CFD. Nuclear Engineering and Design, 2006Search in Google Scholar
11 Bharj, J. S.; Sahaya, R. R.: Effect of flow configuration on velocity and temperature distribution of moderator inside 540 MWe PHWR calandria using CFD techniques. Proceedings of ICAPP'06, USA, June 4–8, 2006Search in Google Scholar
12 Dinesh, M. H.; Ravi, S. D.; Premkumar, G.; Rajan, N. K.: Limiting Thermal Dissipation in a Typical Calandria Based Nuclear Reactor. Proceeding of international conference on Advances in Mechanical Engineering, Gujarat, December 15–17, 2008Search in Google Scholar
13 CFD-ACE Manual, 2009Search in Google Scholar
14 Versteeg, H. K.; Malalasekara, W.: An Introduction to Computational Fluid Dynamics. Longman Scientific and Technical, UK (1995)Search in Google Scholar
© 2011, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Comparison between CAREB code calculations and LOCA test results in the FUMEX III project
- Calculation of moderator circulation in IPHWR using a porosity approach
- Simulation of natural circulation in a rectangular loop using CFD code PHOENICS
- CFD analysis of passive autocatalytic recombiner interaction with atmosphere
- Review and investigations of oscillatory flow behaviour of a horizontal ceiling opening for nuclear containment and fire safety analysis
- CFD simulation of thermal discharge behaviour in the Kadra reservoir at the Kaiga atomic power station
- Inverse problems using Artificial Neural Networks in long range atmospheric dispersion
- Sipping tests for the irradiated fuel elements of the TR-2 research reactor
- Neutron multiplication in source driven subcritical nuclear systems
- Cyclotron production of 101Pd/101mRh radionuclide generator for radioimmunotherapy
- Investigation of cross sections of reactions used in neutron activation analysis
- Modified UN method for the reflected critical slab problem with forward and backward scattering
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Comparison between CAREB code calculations and LOCA test results in the FUMEX III project
- Calculation of moderator circulation in IPHWR using a porosity approach
- Simulation of natural circulation in a rectangular loop using CFD code PHOENICS
- CFD analysis of passive autocatalytic recombiner interaction with atmosphere
- Review and investigations of oscillatory flow behaviour of a horizontal ceiling opening for nuclear containment and fire safety analysis
- CFD simulation of thermal discharge behaviour in the Kadra reservoir at the Kaiga atomic power station
- Inverse problems using Artificial Neural Networks in long range atmospheric dispersion
- Sipping tests for the irradiated fuel elements of the TR-2 research reactor
- Neutron multiplication in source driven subcritical nuclear systems
- Cyclotron production of 101Pd/101mRh radionuclide generator for radioimmunotherapy
- Investigation of cross sections of reactions used in neutron activation analysis
- Modified UN method for the reflected critical slab problem with forward and backward scattering
