Studies on the behaviour of a passive containment cooling system for the Indian Advanced Heavy Water Reactor
-
N. K. Maheshwari
,
D. Saha
Abstract
A passive containment cooling system has been proposed for the advanced heavy water reactor being designed in India. This is to provide long term cooling for the reactor containment following a loss of coolant accident. The system removes energy released into the containment through immersed condensers kept in a pool of water. An important aspect of immersed condenser’s working is the potential degradation of immersed condenser’s performance due to the presence of noncondensable gases. An experimental programme to investigate the passive containment cooling system behaviour and performance has been undertaken in a phased manner. In the first phase, system response tests were conducted on a small scale model to understand the phenomena involved. Tests were conducted with constant energy input rate and with varying energy input rate simulating decay heat. With constant energy input rate, pressures in volume V1 and V2 reached almost steady value. With varying energy input rate V1 pressure dropped below the pressure in V2. The system could efficiently purge air from V1 to V2. The paper deals with the details of the tests conducted and the results obtained.
Abstract
Ein passives Containment-Kühlsystem wird vorgeschlagen für den fortgeschrittenen Schwerwasserreaktor, der zur Zeit in Indien entwickelt wird. Auf diese Weise wird bei einem Störfall durch Kühlmittelverlust eine Langzeitkühlung für das Reaktor-Containment bewirkt. Das System führt durch Tauchkondenser Energie in einen Wassertank ab. Ein wichtiger Aspekt bei dieser Methode ist die potentielle Degradation der Tauchkondenser-Leistung durch das Vorhandensein nichtkondensierbarer Gase. Ein experimentelles Programm zur Untersuchung des Verhaltens und der Leistung des passiven Containment-Kühlsystems wurde in verschiedenen Phasen durchgeführt. In der ersten Phase wurden System-Response-Tests mit einem verkleinerten Modell durchgeführt, um so die beteiligten Phänomene zu verstehen. Die Tests wurden sowohl mit konstanter Eingangsenergie wie auch mit variablen Eingangsenergien zur Simulation des Wärmerückgangs durchgeführt. Bei konstanter Eingangsenergie befanden sich der Druck im Volumen V1 und V2 fast im Gleichgewicht. Bei verschiedenen Eingangsenergien fiel der Druck in V1 unter den Druck in V2 und das System konnte wirkungsvoll Luft von V1 nach V2 abführen. In der Arbeit wird ausführlich über die durchgeführten Tests und deren Ergebnisse berichtet.
Nomenclature
- F:
Flow
- Fi:
Initial flow
- h:
Submerged depth
- Pa:
Air partial pressure
- Pt:
Total pressure
- Ps:
Saturation pressure
References
1 Kakodkar, A.; Sinha, R.K. and Dhawan, M.L.: General Description of Advanced Heavy Water Reactor. Proceeding of a Symposium, IAEA-TECDOC-1117, Seoul, 30 November–4 December, 1998Search in Google Scholar
2 Hirohide Oikawa et al.: Heat Removal Performance Evaluation of Several Passive Containment Cooling Systems During Loss of Coolant Accident. J. of Nucl. Science & Technology 28 199110.1080/18811248.1991.9731450Search in Google Scholar
3 Gangloff, W.: Westinghouse AP600 Advanced Nuclear Plant Design. Proceeding of a Symposium, IAEA-TECDOC-1117, Seoul, 30 November–4 December, 1998Search in Google Scholar
4 Brandani, M. et al.: SBWR – Isolation Condenser and Passive Containment Cooling: An Approach to Passive safety. Proceeding ofSearch in Google Scholar
5 IAEATCM, Brettschuh, WIAEA-.: SWR TECDOC-1000 – An 677Advanced , Rome, Sept. Boiling 1991 Water Reactor with Passive Safety Features. Proceeding of a Symposium, IAEA-TECDOC-1117, Seoul, 30 November–4 December, 1998Search in Google Scholar
6 Otonari, J.; Arai, K.; Oikawa, H. and Nagasaka, H.: Evaluation of Passive Containment Cooling System Performance for Simplified BWR. Proc. Of ANS Winter Meeting, Tokyo, November 1989Search in Google Scholar
7 Seliechi, Yokobori et al.: System Response Test of Isolation Condenser Applied as a Passive Containment Cooling System. The 1st JSME/ASME Joint International Conference on Nuclear Engineering, Tokyo, November, 1991Search in Google Scholar
8 Bandurski, Th. et al.: PANDA Passive Decay Heat Removal Transient Test results. Eighth International Proceedings on Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Vol. 1, Japan, 30 Sept–4 Oct., 1997Search in Google Scholar
9 Vierow, K. M and Schrock, V: Condensation in a natural Circulation Loop with Noncondensable Gases, Part 1– Heat Transfer. Proc. Int. Conf. Multiphase Flows, Tsukaba, Japan, September 1991Search in Google Scholar
10 Khun, S. Z.; Schrock, V E. and Peterson, P. F.: An investigation of Condensation from Steam-Gas Mixture Flowing downward inside a vertical tube. Proceedings of the 7th Int. Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7, NUREG/CP-0142, Vol 1 New York, 199510.2172/106998Search in Google Scholar
11 Siddique M.; Golay M. W. and Kazimi M. S.: “Local heat transfer Coefficients for forced Convection Condensation of Steam in a Vertical tube in the Presence of a Non-Condensable Gas,” Nucl. Technology, Vol. 102, 199310.13182/NT93-A17037Search in Google Scholar
12 Nagasaka, H.; Yamada, K.; Katoh, M. and Yokobori, S.: Heat Removal Tests of Isolation Condenser Applied as a Passive Containment Cooling System. Proceedings of 1st JSME/ASME Int. Conf. On Nuclear Engineering (ICONE-1), Tokyo, November 1991Search in Google Scholar
13 Masoni, P.; Achilli, A.; Billig, P. F.; Botti, S.; Cattadori, G and Silverii Siet, R.: Tests on Full-Scale Prototypical Passive Condensers for SBWR Application. IAEA TCM, IAEA-TECDOC-872, Piacenza, Italy, May 1995Search in Google Scholar
© 2001 Carl Hanser Verlag, München
Articles in the same Issue
- Frontmatter
- Calendar of Events
- Calendar of Events • Veranstaltungskalender
- Summaries
- Summaries/Kurzfassungen
- Notes
- Richtlinie VDI 3783 Blatt 12. Umweltmeteorologie – Physikalische Modellierung von Strömungs- und Ausbreitungsvorgängen in der atmosphärischen Grenzschicht – Windkanalanwendungen; Hrsg.: VDI Verein Deutscher Ingenieure, Kommission Reinhaltung der Luft (KRdl im VDI und DIN-Normenausschuss), Dezember 2000; 107,60 DM
- Comparison of plant efficiencies of various power conversion systems for high-temperature reactor modules
- Studies on the behaviour of a passive containment cooling system for the Indian Advanced Heavy Water Reactor
- Detonation waves in melt-coolant interaction
- Experimental study of the transient characteristics of a natural circulation loop under SBLOCA
- Calculation of the higher order eigenvalues for a homogeneous sphere using the FN method
- Books
- Safe Management of the Operating Lifetimes of Nuclear Power Plants
- Study of the possibility of high accuracy flow measurements with the pulsed neutron activation method
- The astrophysical S-factor for dd-reactions at keV-energy range
- Books
- Books • Bücher
- Monte Carlo analysis of accelerator-driven systems: Studies on spallation neutron yield and energy gain
- Subcritical nuclear systems and their stability against changes in the geometrical set-up
- Technical Notes
- An energy amplifier fluidized bed nuclear reactor concept
- An attempt to describe the swelling of U3Si 2 fuel by a simple formula
- European Commission initiative to promote technical harmonisation on risk-based decision making
- Patent
- Notes
- Note • Mitteilung
Articles in the same Issue
- Frontmatter
- Calendar of Events
- Calendar of Events • Veranstaltungskalender
- Summaries
- Summaries/Kurzfassungen
- Notes
- Richtlinie VDI 3783 Blatt 12. Umweltmeteorologie – Physikalische Modellierung von Strömungs- und Ausbreitungsvorgängen in der atmosphärischen Grenzschicht – Windkanalanwendungen; Hrsg.: VDI Verein Deutscher Ingenieure, Kommission Reinhaltung der Luft (KRdl im VDI und DIN-Normenausschuss), Dezember 2000; 107,60 DM
- Comparison of plant efficiencies of various power conversion systems for high-temperature reactor modules
- Studies on the behaviour of a passive containment cooling system for the Indian Advanced Heavy Water Reactor
- Detonation waves in melt-coolant interaction
- Experimental study of the transient characteristics of a natural circulation loop under SBLOCA
- Calculation of the higher order eigenvalues for a homogeneous sphere using the FN method
- Books
- Safe Management of the Operating Lifetimes of Nuclear Power Plants
- Study of the possibility of high accuracy flow measurements with the pulsed neutron activation method
- The astrophysical S-factor for dd-reactions at keV-energy range
- Books
- Books • Bücher
- Monte Carlo analysis of accelerator-driven systems: Studies on spallation neutron yield and energy gain
- Subcritical nuclear systems and their stability against changes in the geometrical set-up
- Technical Notes
- An energy amplifier fluidized bed nuclear reactor concept
- An attempt to describe the swelling of U3Si 2 fuel by a simple formula
- European Commission initiative to promote technical harmonisation on risk-based decision making
- Patent
- Notes
- Note • Mitteilung
