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7 - Reactor Multiphase Flows and Accidents

Published online by Cambridge University Press:  05 April 2016

Christopher Earls Brennen
Christopher Earls Brennen
Affiliation:
California Institute of Technology
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Summary

Multiphase Flows in Nuclear Reactors

This and the following sections will include descriptions of how multiphase flow is pertinent to the understanding and analysis of nuclear power generation and nuclear reactor accidents. The focus is on those multiphase issues that arise in the reactor itself, though, of course, there are many multiphase flow issues associated with the conventional components of the power generation process such as the steam generators and steam turbines.

Multiphase flows that might or do occur in a nuclear reactor are most conveniently subdivided into those that occur during nominal reactor operation and those that might occur and have occurred during a reactor accident. Both sets of issues are complex and multifaceted, and many of the complexities are beyond the scope of this monograph. The reader is referred to texts such as Hsu and Graham (1976), Jones and Bankhoff (1977a, 1977b), Jones (1981), Hewitt and Collier (1987), and Todres and Kazimi (1990) for a broader perspective on these issues.

Multiphase Flow in Normal Operation

The most obvious multiphase flow occurring during normal operation is the process of boiling in a BWR core. Sections 6.5.4, 6.5.5, and 6.5.6 described how boiling is initiated within a BWR reactor core (Section 6.5.3), how the flow pattern within the coolant passages would change from bubbly flow to annular flow as the fluid rose (Section 6.2.3), and the circumstances under which the wall film might undergo burnout (Section 6.5.4), leading to the critical heat flux condition (CHF) and a rapid rise in the temperature (Figure 6.9) of the interface between the fuel rod cladding and the coolant. Boiling water reactors are designed to operate at a comfortable margin short of CHF at any location within the reactor. This requires a coupled calculation of the multiphase flow and the neutronics (Section 5.5) as well as a criterion that determines the CHF. For a review of the thermohydraulic data on CHF in nuclear reactors, the reader is referred to Groeneveld and Gardiner (1977).

Void Fraction Effect on Reactivity

In most reactors, it is important to recognize that any change in the geometry of the core or change of phase of its components may alter the reactivity of the reactor.

Type
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Thermo-Hydraulics of Nuclear Reactors , pp. 127 - 150
Publisher: Cambridge University Press
Print publication year: 2016

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References

Aerojet Nuclear Company (1976). RELAP4/MOD5: A computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems (3 volumes). ANCRNUREG 1335.
Board, S. J., and Caldarola, L. (1977). Fuel coolant interactions in fast reactors. In Symposium on the thermal and hydraulic aspects of nuclear reactor safety. Volume 2: Liquid metal fast breeder reactors, pp. 195–222 (eds.O. C., Jones and S.G., Bankhoff). ASME.
Bodansky, D. (1996). Nuclear energy: Principles, practices and prospects. Springer-Verlag.
Brennen, C. E. (1994). Hydrodynamics of pumps. Concepts ETI/Oxford University Press.
Brennen, C. E. (1995). Cavitation and bubble dynamics. Oxford University Press.
Brennen, C. E. (2005). Fundamentals of multiphase flow. Cambridge University Press.
Burgess, D. S., Biordi, J., and Murphy, J. (1972). Hazards of spillage of LNG into water. U.S. Bureau of Mines, PMSRC Rep. 4177.
Cameron, I. R. (1982). Nuclear fission reactors. Plenum Press.
Colgate, S. A., and Sigurgeirsson, T. (1973). Dynamic mixing of water and lava. Nature, 244, 552–55.Google Scholar
Collier, J.G., and Hewitt, G. F. (1987). Introduction to nuclear power. Hemisphere.
Dickerman, C. E., Barts, E.W., De Volpi, A., Holtz, R. E., Murphy, W. F., and Rothman, A. B. (1976). Recent results from TREAT tests on fuel, cladding and coolant motion. Annals of Nuclear Energy, 3, 315–22.Google Scholar
Dix, G. E., and Andersen, J.G.M. (1977). Spray cooling heat transfer for a BWR fuel bundle. In Symposium on the thermal and hydraulic aspects of nuclear reactor safety.Volume 1: Light water reactors (eds.O. C., Jones and S.G., Bankhoff).ASME.
Fauske, H. K., (1976). The role of core disruptive accidents in design and licensing of LMFBR's. Nuclear Safety, 17, 550–67.Google Scholar
Fauske, H.K. (1977). Liquid metal fast breeder reactor safety:An overview including implications of alternate fuel cycles. No. CONF-771120-22. Argonne National Lab., Ill.
Fauske, H.K. (1981). Core disruptive accidents. In Nuclear reactor safety heat transfer, pp. 481–94 (ed.O. C., Jones). Singapore: Hemisphere.
Fauske, H. K., and Koyama, K. (2002). Assessment of fuel coolant interactions (FCIs) in the FBR core disruptive accident (CDA). Journal of Nuclear Science and Technology, 39, 608–14.Google Scholar
Frost, D., and Sturtevant, B. (1986). Effects of ambient pressure on the instability of a liquid boiling explosively at the superheat limit. ASME Journal of Heat Transfer, 108, 418–24.Google Scholar
Grandjean, C. (2007). Coolability of blocked regions in a rod bundle after ballooning under LOCAconditions—Main findings froma review of past experimental programmes. Nuclear Engineering and Design, 237, 1872–86.Google Scholar
Groeneveld, D.C., and Gardiner, S.R.M. (1977). Post-CHF heat transfer under forced convective conditions. In Symposium on the thermal and hydraulic aspects of nuclear reactor safety. Volume 1: Light water reactors, pp. 43–73 (eds.O. C., Jones and S.G., Bankhoff).ASME.
Hassan, Y. A. (1986). Analysis of FLECHT and FLECHT-SEASET reflood tests with RELAP5 MOD2. Nuclear Technology, 74, 176–88.Google Scholar
Hewitt, G. F., and Collier, J.G. (1987). Introduction to nuclear power. Taylor and Francis.
Hochreiter, L. E. (1985). FLECHT SEASET program final report. NUREG/CR-4167.
Hochreiter, L. E., and Riedle, K. (1977). Reflood heat transfer and hydraulics in pressurized water reactors. In Symposium on the thermal and hydraulic aspects of nuclear reactor safety. Volume 1: Light water reactors, pp. 75–107 (eds.O. C., Jones and S.G., Bankhoff).ASME.
Holowach, M.J., Hochreiter, L. E., Cheung, F.B., Aumiller, D. L., and Houser, R. J. (2003). Scaling of quench front and entrainment-related phenomena. Nuclear Engineering and Design, 223, 197–209.Google Scholar
Hsu, Y.-Y. (1978). Two-phase problems in PWRs. In Two phase flows in nuclear reactors, vol. 1, Von Karman Institute for Fluid Dynamics Vol. 1, 19–34.
Hsu, Y.-Y., and Graham, R.W. (1976). Transport processes in boiling and two-phase systems. Hemisphere/McGraw-Hill.
Hsu, Y.-Y., and Sullivan, H. (1977). Thermal hydraulic aspects of PWRsafety research. In Symposium on the thermal and hydraulic aspects of nuclear reactor safety.Volume 1: Light water reactors, pp. 1–15 (eds.O. C., Jones and S.G., Bankhoff).ASME.
IEAA (2015). Safety case study: The Three Mile Island accident. http://www.iaea.org/ns/tutorials/regcontrol/assess/assess3233.htm.
Jackson, J. F., Liles, D. R., Ransom, D. H., and Ybarrondo, L. J. (1981). LWR system safety analysis. Nuclear Reactor Safety Heat Transfer, 12, 415.Google Scholar
Johnston, R. (2007). Deadliest radiation accidents and other events causing radiation casualties. Database of Radiological Incidents and Related Events. See also http://en.m.wikipedia.org/ wiki/Nuclear_submarine\#Accidents.
Jones, O. C. (ed.) (1981). Nuclear reactor safety heat transfer. Hemisphere.
Jones, O.C., and Bankhoff, S.G. (eds.) (1977a). Symposium on the thermal and hydraulic aspects of nuclear reactor safety. Volume 1: Light water reactors. ASME.
Jones, O.C., and Bankhoff, S.G. (eds.) (1977b). Symposium on the thermal and hydraulic aspects of nuclear reactor safety. Volume 2: Liquid metal fast breeder reactors. ASME.
Knief|R. A. (1992). Nuclear engineering: Theory and practice of commercial nuclear power. Hemisphere.
Lahey, R. T., Jr. (1977). The status of boiling water nuclear reactor safety analysis. In Symposium on the thermal and hydraulic aspects of nuclear reactor safety. Volume 1: Light water reactors (eds.O. C., Jones and S.G., Bankhoff).ASME.Google Scholar
Lewis, E. E. (1977). Nuclear power reactor safety. John Wiley.
Long, G. (1957). Explosions of molten aluminum in water: Cause and prevention. Metal Progress, 75, 107–12.Google Scholar
Marples, D. R. (1986). Chernobyl and nuclear power in the USSR. St.Martin's Press.
Mould, R. F. (2000). Chernobyl record: The definitive history of the Chernobyl catastrophe. Institute of Physics.
OCED. (1996). Implementing severe accident management in nuclear power plants. Nuclear Energy Agency, OCED.
Okrent, D. (1981). Nuclear reactor safety. University of Wisconsin Press.
Osif, B.A., Baratta, A. J.; and Conkling, T.W. (2004). TMI 25 years later: The Three Mile Island nuclear power plant accident and its impact. Pennsylvania State University Press.
Schultz, M.A. (1955.) Control of nuclear reactors and power plants. McGraw-Hill.
TEPCO. (2011). Tokyo Electric Power Company. http://photo.tepco.co.jp/date/2011/201105j/110519-01j.html.
Todres, N. E., and Kazimi, M. S. (1990). Nuclear systems I. Thermal hydraulic fundamentals. Hemisphere.
UNSCEAR (2000). Exposures and effects of theChernobyl accident. United Nations Scientific Committee on the Effects of Atomic Radiation UNSCEAR 2000 Rep. 2, Annex J.
USAEC (1957). Theoretical possibilities and consequences of major accidents in large nuclear power plants. U.S. Atomic Energy Commission Rep.WASH-740.
USAEC(1973). The safety of nuclear power reactors (light water cooled) and related facilities. U.S. Atomic Energy Commission Rep.WASH-1250.
USNRC (1975). Reactor safety study: An assessment of accident risks in U.S. commercial nuclear power plants. U.S. Nuclear Regulatory Commission Rep.WASH-1400.
USNRC(2006). Safety culture and changes to theROP. Inspector counterpart training session, May–June 2006. http://pbadupws.nrc.gov/docs/ML0615/ML061590145.pdf.
Wagner, R. J., and Ransom, V. H. (1982). RELAP5 nuclear-plant analyzer capabilities. Transactions of the American Nuclear Society, 43, 381–82.Google Scholar
Wilson, R. (1977). Physics of liquidmetal fast breeder reactor safety. Review of Modern Physics, 49, 893–924.Google Scholar
Windscale Accident (2015). http://en.wikipedia.org/wiki/Windscale_fire.
Witte, L. C., Cox, J. E., and Bouvier, J. E. (1970). The vapour explosion. Journal of Metals, 22, 39–44.Google Scholar
Witte, L. C., Vyas, T. J., and Gelabert, A. A. (1973). Heat transfer and fragmentation during molten-metal/water interactions. ASME Journal of Heat Transfer, 95, 521–27.Google Scholar
WNA. (2014). Fukushima accident. http://www.world-nuclear.org/info/Safety-and-Security/Safety-of-Plants/Fukushima-Accident/.

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