Numerical study on two-phase flow instability in multi-parallel channels of helical-coiled once-through steam generator of lead-cooled fast reactor
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The helical-coiled once-through steam generator (H-OTSG) has the advantages of compact structure and strong heat transfer ability, and is appropriate for lead-cooled fast reactor. The two-phase flow instability may cause mechanical vibration and thermal fatigue of heat transfer tube bundles, posing a serious threat to the safe operation of the H-OTSG. In this work, the secondary side of the H-OTSG characterized as multi-parallel channels is modeled by RELAP5/MOD3.4 code, and the oscillation behavior during start-up and the influence of structural and operating parameters on system stability are studied based on time-domain method. The results indicate that the pressure, flow rate, and temperature of the secondary fluid exhibit density wave oscillations at the heating section in a (n-2,2) pattern. In addition, increasing inlet throttling, reducing outlet throttling, controlling subcooling within an appropriate range and avoiding operation under low loads are all beneficial for improving the system stability of the helical-coiled once-through steam generator
Abstract
The helical-coiled once-through steam generator (H-OTSG) has the advantages of compact structure and strong heat transfer ability, and is appropriate for lead-cooled fast reactor. The two-phase flow instability may cause mechanical vibration and thermal fatigue of heat transfer tube bundles, posing a serious threat to the safe operation of the H-OTSG. In this work, the secondary side of the H-OTSG characterized as multi-parallel channels is modeled by RELAP5/MOD3.4 code, and the oscillation behavior during start-up and the influence of structural and operating parameters on system stability are studied based on time-domain method. The results indicate that the pressure, flow rate, and temperature of the secondary fluid exhibit density wave oscillations at the heating section in a (n-2,2) pattern. In addition, increasing inlet throttling, reducing outlet throttling, controlling subcooling within an appropriate range and avoiding operation under low loads are all beneficial for improving the system stability of the helical-coiled once-through steam generator
참고문헌 (19)
- Lead-cooled fast reactor (LFR) design: safety, neutronics, thermal hydraulics, structural mechanics, fuel, core, and plant design, "C. Smith", Lawrence Livermore Natl. Lab, 7~, pp.LLNL-BOOK-424323 (2010)
- J. A. Boure, "Review of two-phase flow instability", Nucl. Eng. Des, 25, pp.165~192 (1973)
- D. Papini, "Experimental characterization of two-phase flow instability thresholds in helically coiled parallel channels", International Congress on Advances in Nuclear Power Plants (ICAPP), pp.1843~1852 (2011)
- D. Papini, "On Density Wave Instability Phenomena - Modelling and Experimental Investigation", Two Phase Flow, Phase Change and Numerical patternling, 257~284 (2011)
- Experimental Investigation of Thermal Hydraulic Instabilities in Steam Senerator Helically Coiled Tubes, "M. Colombo", ENEA, ~, pp.CERSE-POLIMI RL-1355 (2011), 2
- D. Papini, "Experimental and theoretical studies on density wave instabilities in helically coiled tubes", Int. J. Heat Mass Tran, 68, pp.343~356 (2014)
- R. Yang, "An experimental study of two-phase flow instability in a parallel helically coiled tube system", J. Eng. Thermophys, 14(1), pp.84~87 (1993)
- R. Yang, "Modeling experimental study of two-phase flow instability in parallel coil evaporating tubes", J. Eng. Thermophys, 15(1), pp.84~88 (1994)
- M. Wang, "Experimental and numerical studies on two-phase flow instability behavior of a parallel helically coiled system", Ann. Nucl. Energy, 144, pp.107588~ (2020)
- Z. Xu, "Development of a RELAP5 model for the thermohydraulic characteristics simulation of the helically coiled tubes", Ann. Nucl. Energy, 153, pp.108032~ (2021)
- R. Dong, "Modeling analyses of two-phase flow instabilities for straight and helical tubes in nuclear power plants", Nucl. Eng. Des, 307, pp.205~217 (2016)
- J. Hao, "Analysis of density wave oscillations in helically coiled tube once-through steam generator", Sci. Technol. Nucl. Ins, pp.3071686~ (2016)
- G. Xia, "Research of two-phase flow instability in parallel narrow multi-channel system", Ann. Nucl. Energy, 48, pp.1~16 (2012)
- H. Qian, "Design of digital nuclear power small reactor once-through steam generator control system", Nucl. Eng. Technol, 54, pp.2435~2443 (2022)
- K. Fukuda, "Study on two-phase flow instability in parallel multi-channels", Heat Tran. Jpn. Res, 23(8), pp.259~266 (1996)
- K. Takitanit, "Density wave instability in once-through boiling flow system, (III): distributed parameter model", J. Nucl. Sci. Technol, 16(1), pp.16~29 (1979)
- N. Jiang, "Flow instability analysis of natural circulation under ERVC condition for SMR", Prog. Nucl. Energy, 117, pp.103063~ (2019)
- W. Fu, "Investigation on tow-phase flow density wave instability in parallel once-through evaporation tubes", J. Eng. Thermophys, 35(3), pp.576~580 (2014)
- Y. Zhao, "Research on Operation Characteristics of the Flashing-Driven Natural Circulation Integrated Reactor", pp.2020
