Coolant mixing in a pressurized water reactor: Deboration transients, steam-line breaks, and emergency core cooling injection

Nuclear Technology

Volumn 143, Issue 1, 2003, Pages 37-56

  Prasser, Horst Michael ^a   Grunwald, Gerhard ^a   Höhne, Thomas ^a   Kliem, Sören ^a   Rohde, Ulrich ^a   Weiss, Frank Peter ^a  

^a INSTITUTE OF ION BEAM PHYSICS AND MATERIALS RESEARCH   (Germany)

Author keywords

Boron dilution transients; Coolant mixing; Pressurized water reactors

Indexed keywords

ACCIDENT PREVENTION; COMPUTATIONAL FLUID DYNAMICS; COOLANTS; PRESSURE VESSELS;

EMERGENCY CORE COOLING (ECC) INJECTION;

PRESSURIZED WATER REACTORS;

EID: 0037559501     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT03-A3396     Document Type: Article

References (27)

1. U. GRUNDMANN and U. ROHDE, "Investigations on a Boron Dilution Accident for a VVER-440 type Reactor by the Help of the Code DYN3D," Proc. Topi Mtg. Advances in Reactor Physics, Knoxville, Tennessee, April 11-15, 1994, Vol. 3, p. 464, American Nuclear Society (1994).
2. D. ALVAREZ et al., "Three Dimensional Calculations and Experimental Investigations of the Primary Coolant Flow in a 900 MW PWR Vessel," Proc. 5th Int. Topl. Mtg. Reactor Thermal Hydraulics (NURETH-5), Salt Lake City, Utah, September 21-24, 1992, Vol. II, p. 586, American Nuclear Society (1992).
3. F. ALAVYOON, B. HEMSTRÖM, N. G. ANDERSSON, and R. KARLSSON, "Experimental and Computational Approach to Investigating Rapid Boron Dilution Transients in PWRs," presented at Committee on the Safety of Nuclear Installations Specialist Mtg. Boron Dilution Reactivity Transients, State College, Pennsylvania, October 18-20, 1995.
4. O. I. MELIKHOV, V. I. MELIKHOV, S. E. YAKUSH, YU. A. BEZRUKOV, and S. A. LOGVINOV, "Analysis of Boron Dilution in VVER-1000 Reactor," Proc. Annual Mtg. Nuclear Technology 2001, Dresden, Germany, May 15-17, 2001, p. 117, INFORUM GmbH (2001).
5. V. N. ULYANOVSKY et al., "The Mixing of Coolant with Different Boron Concentration at the VVER-1000 Core Inlet During RCP Start-Up," Proc. Annual Mtg. Nuclear Technology 2000, Bonn, Germany, May 23-25, 2000, p. 115, INFORUM GmbH (2000).
6. "HDR Safety Program - Thermal Mixing in the Cold Leg and Downcomer of the HDR Test Rig," PHDR 91-89, Forschungszentrum Karlsruhe (1990).
7. K. UMMINGER, W. KASTNER, J. LIEBERT, and T. MULL, "Thermal Hydraulics of PWR's with Respect to Boron Dilution Phenomena, Experimental Results from the Test Facilities PKL and UPTF," Proc. 9th Int. Topl. Mtg. Nuclear Reactor Thermal Hydraulics (NURETH-9), San Francisco, California, October 3-8, 1999, American Nuclear Society (1999) (CD-ROM).
8. M. GAVRILAS and K. KIGER, "ISP-43: Rapid Boron Dilution Transient Experiment, Comparison Report," NBA/ CSNI/R(2000)22, Nuclear Energy Agency.
9. B. WOODS, "UM 2 × 4 Loop Experimental Findings on the Effect of Inertial and Buoyancy Forces on Annular Flow Mixing for Rapid Boron Dilution Transients," PhD Thesis, University of Maryland (2001).
10. T. HÖHNE, "Vergleich von Kühlmittelströmung und -Vermischung in einem skalierten Modell des DWR Konvoi mit den Vorgängen im Originalreaktor," FZR-210, Forschungszentrum Rossendorf (1998).
11. P. DRÄGER, G. ACKERMANN, and P. SIKLOSSY, "Theoretische und experimentelle Ermittlung der Temperaturverteilung in der Spaltzone des WWER-440," Kernenergie, 28, 7, 293 (1985).
12. P. DRÄGER, "Makroskopische Kühlmittelvermischung in Druckwasserreaktoren," PhD Thesis, TH Zittau (1987).
13. I. D. JOHNSON, "Method and Apparatus for Measuring Water in Crude Oil," U.S. Patent 4,644,263 (Feb. 17, 1987).
14. N. REINECKE, M. BODDEM, G. PETRITSCH, and D. MEWES, "Tomographisches Messen der relativen Phasenanteile in zweiphasigen Strömungen fluider Phasen," Chem. Ing. Tech., 68, 11, 1404 (1996).
15. H.-M. PRASSER, A. BÖTTGER, and J. ZSCHAU, "A New Electrode-Mesh Tomograph for Gas-Liquid Flows," Flow Measurement and Instrumentation, 9, 111 (1998).
16. H.-M. PRASSER, J. ZSCHAU, D. PETERS, G. PIETZSCH, W. TAUBERT, and M. TREPTE, "Fast Wire-Mesh Sensors for Gas-Liquid Flows - Visualization with up to 10000 Frames per Second," Proc. Int. Congress Advanced Nuclear Power Plants (ICAPP), Hollywood, Florida, June 9-13, 2002, American Nuclear Society (2002) (CD-ROM).
17. G. GRUNWALD, TH. HÖHNE, H.-M. PRASSER, and F.-P. WEISS, "Coolant Mixing in PWR at Constant Coolant Flow in the Primary Circuit," Proc. Annual Mtg. Nuclear Technology, Bonn, Germany, May 23-25, 2000, p. 109, INFORUM GmbH (2000).
18. G. GRUNWALD, TH. HÖHNE, and H.-M. PRASSER, "Laser-Doppler-Velocity Measurements in the Downcomer of the ROCOM Test Facility in Comparison with Numerical Results," FZR-334, Forschungszentrum, Rossendorf (2001) (in German).
19. R. HERTLEIN, K. UMMINGER, S. KLIEM, H.-M. PRASSER, T. HÖHNE, and F.-P. WEISS, "Experimental and Numerical Investigation of Boron Dilution Transients in Pressurized Water Reactors," Nucl. Technol., 141, 88 (2003).
20. U. GRUNDMANN and U. ROHDE, "DYN3D - A 3-Dimensional Core Model for Steady-State and Transient Analysis in Thermal Reactors," Proc. Int. Conf. Physics of Reactors (PHYSOR'96), p. J70 (1996).
21. U. GRUNDMANN and U. ROHDE, "Verification of the Code DYN3D/R with the Help of International Benchmarks," FZR-195, Forschungszentrum Rossendorf (1997).
22. R. KYRKI-RAJAMÄKI, U. GRUNDMANN, and A. KERESZTURI, "Results of Three-Dimensional Hexagonal Dynamic Benchmark Problems for WER Type Reactors," Proc. Int. Conf. Physics of Reactors (PHYSOR96), p. J229 (1996).
23. K. N. IVANOV, U. GRUNDMANN, S. MITTAG, and U. ROHDE, "Comparative Study of a Boron Dilution Scenario in WER Reactors," Ann. Nucl. Eng., 26, 1331 (1999).
24. W. TIETSCH and J. TISCHER, "Analysis of Boron Dilution During Small Break LOCAs in a 2 × 4 Loop B&W Type PWR," Proc. Annual Mtg. Nuclear Technology, Karlsruhe, Germany, May 18-21, 1996, p. 143, K. G. BAUER, Ed., INFORUM GmbH (1999).
25. R. REINDERS, "Three-Dimensional Calculation of the Boron Concentration in the Reactor Pressure Vessel After a SG Tube Rupture Accident," Proc. Annual Mtg. Nuclear Technology 1998, p. 107, INFORUM GmbH (1998) (in German).
26. "CFX-4.3 Flow Solver User Guide," AEA Technology (1999).
27. S. KLIEM et al., "ROCOM Experiments on the Influence of Density Differences on the Coolant Mixing Inside the Reactor Pressure Vessel of a PWR," Proc. Annual Mtg. Nuclear Technology 2002, Stuttgart, Germany, May 14-16, 2002, p. 65, INFORUM GmbH (2002).