Modeling the statics of a natural-circulation boiling water reactor loop

Nuclear Technology

Volumn 127, Issue 1, 1999, Pages 38-48

  Kok, Haico V ^a   Van Der Hagen, Tim H J J ^a,b  

^a DELFT UNIVERSITY OF TECHNOLOGY   (Netherlands)

^b Interuniversity Reactor Institute Delft   (Netherlands)

Author keywords

[No Author keywords available]

Indexed keywords

ATMOSPHERICS; COMPUTATIONAL METHODS; COMPUTER SIMULATION; COOLING; CORRELATION METHODS; FRICTION; HYDRAULICS; MASS TRANSFER; MATHEMATICAL MODELS;

DRIFT-FLUX MODEL; THERMAL HYDRAULICS;

BOILING WATER REACTORS;

EID: 0032672394     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT99-A2982     Document Type: Article

References (14)

1. T. H. J. J. VAN DER HAGEN, H. VAN DAM, and H. V. KOK, "The Delft DESIRE Facility for Studies on (Natural Circulation) BWR Primary System Statics & Dynamics," Proc. Int. Topl. Mtg. Research Facilities for the Future of Nuclear Energy, Brussels, Belgium, June 4-6, 1996, p. 365 (1996).
2. R. VAN DE GRAAF, T. H. J. J. VAN DER HAGEN, and R. F. MUDDE, "Scaling Laws and Design Aspects of a Natural-Circulation-Cooled Simulated Boiling Water Reactor Fuel Assembly," Nucl. Technol., 105, 190 (1994).
3. R. VAN DE GRAAF, T. H. J. J. VAN DER HAGEN, and R. F. MUDDE, "Two-Phase Scaling Laws for a Simulated BWR Assembly," Nucl. Eng. Des., 148, 455 (1994).
4. N. E. TODREAS and M. S. KAZIMI, Nuclear Systems 1 - Thermal Hydraulic Fundamentals, Hemisphere Publishing, New York (1990).
5. H. V. KOK, T. H. J. J VAN DER HAGEN, and R. F. MUDDE, "Subchannel Void-Fraction Measurements Using a Simple Gamma-Transmission Method" (to be published).
6. H. V. KOK, "Experiments on a Natural Circulation Loop - from Void-Fraction to Coupled Nuclear Thermal-Hydraulic Dynamics," PhD Thesis, Delft University of Technology, Delft University Press, Delft, The Netherlands (1998).
7. K. LÜTZOW and D. STÄCK, "Experimentelle Untersuchingen zum Mitreißen von Dampfblasen in den Sinkschacht eines Kernheizreaktors mit Naturumlauf," Kernenergie, 30, 114 (1987).
8. K. LÜTZOW and D. WEGNER, "Ein einfaches Modell zur Berechnung des Mitreißens von Dampf in den Sinkschacht eines Kernheizreaktors," Kernenergie, 30, 442 (1987).
9. K. LÜTZOW and D. WEGNER, "Verhalten der Zweiphasenströmung im oberen Umlenkbereich eines naturumlaufgekühlten Siedewasserreaktors in Integralbauweise," Kernenergie, 33, 133 (1990).
10. M. HIDAKA and H. SUZUKI, "Experimental Study on Gas Carry-Under in Down Flow from Two-Phase Mixture." J. Nucl. Sci. Technol., 27, 1065 (1990).
11. J. A. A. WOUTERS, F. J. VAN DER KAA, P. OPPENTOCHT, and W. H. M. NISSEN, "Data and Analysis of Two Identical Water Level Experiments at the Dodewaard Natural Circulation BWR," 14573-TFO 92-3012, Keuring van Electrotechnische Materialen Arnhem, Arnhem, The Netherlands (1992).
12. J. A. A. WOUTERS, F. J. VAN DER KAA, P. OPPENTOCHT, and W. H. M. NISSEN, "The Effect of Water Level on the Behavior of the Dodewaard Natural Circulation BWR," Proc. Int. Conf. Design and Safety of Advanced Nuclear Power Plants, Tokyo, Japan, October 25-29, 1992 (1992).
13. T. H. J. J. VAN DER HAGEN, F. J. VAN DER KAA, J. KARUZA, W. H. M. NISSEN, A. J. C. STEKELENBURG, and J. A. A. WOUTERS, "Measurements at Various Pressures at the Dodewaard Natural Circulation Boiling Water Reactor in Cycle 23," GKN-93-023/FY/R, Gemeenschappelijke Kernenergiecentrale Nederland, Dodewaard, The Netherlands (1993).
14. R. T. LAHEY, Jr., and F. J. MOODY, The Thermal-Hydraulics of a Boiling Water Nuclear Reactor, American Nuclear Society, La Grange Park, Illinois (1993).