核反应堆蒸汽发生器两相流不稳定性现象规律、研究方法及应用

苏阳; 李晓伟; 吴莘馨; 张作义

doi:10.16511/j.cnki.qhdxxb.2023.25.042

PDF(6631 KB)

清华大学学报（自然科学版） ›› 2023, Vol. 63 ›› Issue (8) : 1184-1203. DOI: 10.16511/j.cnki.qhdxxb.2023.25.042

论文

核反应堆蒸汽发生器两相流不稳定性现象规律、研究方法及应用

苏阳, 李晓伟, 吴莘馨, 张作义

作者信息 +

Phenomenon, method, and application of the two-phase flow instability in a nuclear reactor steam generator

SU Yang, LI Xiaowei, WU Xinxin, ZHANG Zuoyi

Author information +

文章历史 +

摘要

核反应堆蒸汽发生器二次侧的流动不稳定现象不仅会影响控制系统，而且会使设备结构的压力边界疲劳损坏。两相流不稳定性的表现形式多样、影响因素众多、机理复杂、研究方法种类多，一直是蒸汽发生器和两相流领域的经典问题之一。首先，该文介绍了两相流不稳定性的常见分类和3种典型不稳定性的机理，包括流量漂移、密度波型脉动和压力降型脉动。其次，从守恒方程出发，总结了各种研究方法。再次，系统性总结了3种典型不稳定性的研究现状，并重点介绍了清华大学核能与新能源技术研究院堆工团队的工作。然后，该文提出了使用新无量纲数描述复杂过热系统，包括两相数、过热数、无量纲泵数和无量纲旁通数，明确和统一了Froude数、摩擦数、管长和管径等对密度波型脉动的影响规律，并解释了此前研究中矛盾的结论。同时，该文给出了有关模型简化和边界条件对稳定边界影响的理论推导和证明，并明确了实验室小规模单管或简化并联管试验段及工程验证试验回路与实际核电厂蒸汽发生器及二回路系统之间的替代条件。最后，该文介绍了高温气冷堆示范工程（high temperature gas-cooled reactor-pebble bed module，HTR-PM）蒸汽发生器如何通过设计来避免不稳定性问题。

Abstract

[Significance] Two-phase flow instability is a classic problem in the field of steam generators and other two-phase flows. Therefore, it has been studied extensively. In nuclear reactor steam generators, two-phase flow instability may occur on the secondary side and interfere with the control system, causing fatigue-induced damage to the equipment. While two-phase flow instability can have different complex mechanisms and many influencing factors, there are various methods to research and analyze this phenomenon.[Progress] The phenomenon of two-phase flow instability can be classified into two types. The mechanisms of flow excursion (LE), density wave oscillation (DWO) and pressure drop oscillation (PDO) are introduced. LE and PDO can occur in conditions corresponding to the region of negative slope in the hydrodynamic characteristic curve (mass flow rate vs. pressure drop curve) in the heated tube and can be avoided by eliminating the negative slope region. However, DWO can also occur in the positive slope region due to the phase difference between two transient processes. One of these is the mass flow rate variation caused by variation in the driving pressure difference, which is controlled by the rate of momentum transfer. The other is the transient variation of the subcooled water region length and the density of saturated two-phase region fluid, which is caused by heat transfer. Changes caused by heat transfer are slower than changes in flow and pressure. Various research methods of two-phase flow instability are systematically summarized, including the theoretical time-domain method (nonlinear and linear methods), theoretical frequency-domain method, and discrete numerical method, starting from the conservation equations. The mathematical criterion obtained from the theoretical time-domain model can analyze the parameters' influence exactly over a wide range. The spatial distribution of density, enthalpy, and other physical parameters in the frequency domain can be obtained using the theoretical frequency-domain method, and the stability boundary it predicts is more accurate than that predicted by the theoretically simplified linear time-domain method. In addition, the research status of LE, DWO, and PDO is systematically summarized, with a particular focus on the work of our research group. New dimensionless numbers (two-phase number, superheated number, dimensionless pump number, and dimensionless bypass number) are proposed to describe the stability of the complex, superheated, two-phase flow boiling systems. A law unifying the influence of the Froude number, friction number, and geometric parameters (tube length, tube diameter, etc.) on DWO was developed. Previous contradictory conclusions are explained. A rigorous theoretical derivation and proof of the effects of model simplification and boundary conditions are presented. The requirements for conservatively modeling a real nuclear power plant steam generator and secondary loop system using a test section consisting of a single or multiple parallel small-scale heated tubes and a simplified engineering verification test loop in the laboratory are clarified. Finally, methods to avoid LE and DWO in the steam generator of the high-temperature gas-cooled reactor are introduced based on reactor design. To predict the stability of the high-temperature gas-cooled reactor-pebble bed module (HTR-PM) engineering test facility-steam generator (ETF-SG), theoretical time-domain method, theoretical frequency-domain method, RELAP5 model, and one-dimensional transient program are developed, which are in good agreement with the experiments.[Conclusion and Prospects] The results from the ETF-SG can conservatively predict the stability boundary of the steam generator and secondary loop of the HTR-PM nuclear power plant. The conditions for the occurrence of in-phase and out-of-phase DWO in ETF-SG are revealed, and methods for eliminating them are recommended. The above achievements are applied in the design, commissioning, and operation of the HTR-PM steam generator.

导出引用

苏阳, 李晓伟, 吴莘馨, 张作义. 核反应堆蒸汽发生器两相流不稳定性现象规律、研究方法及应用[J]. 清华大学学报（自然科学版）. 2023, 63(8): 1184-1203 https://doi.org/10.16511/j.cnki.qhdxxb.2023.25.042

SU Yang, LI Xiaowei, WU Xinxin, ZHANG Zuoyi. Phenomenon, method, and application of the two-phase flow instability in a nuclear reactor steam generator[J]. Journal of Tsinghua University(Science and Technology). 2023, 63(8): 1184-1203 https://doi.org/10.16511/j.cnki.qhdxxb.2023.25.042

参考文献

[1] ZHANG Z Y, WU Z X, WANG D Z, et al. Current status and technical description of Chinese 2×250MW_th HTR-PM demonstration plant[J]. Nuclear Engineering and Design, 2009, 239(7):1212-1219.
[2] ZHANG Z Y, DONG Y J, LI F, et al. The Shandong Shidao Bay 200MW_e high-temperature gas-cooled reactor pebble-bed module (HTR-PM) demonstration power plant:An engineering and technological innovation[J]. Engineering, 2016, 2(1):112-118.
[3] ZHANG Z Y, SUN Y L. Economic potential of modular reactor nuclear power plants based on the Chinese HTR-PM project[J]. Nuclear Engineering and Design, 2007, 237(23):2265-2274.
[4] 李晓伟, 吴莘馨, 张作义. 高温气冷堆螺旋管式直流蒸汽发生器热工水力学[J]. 原子能科学技术, 2019, 53(10):1906-1917. LI X W, WU X X, ZHANG Z Y. Thermal hydraulics of HTGR helical tube once through steam generator[J]. Atomic Energy Science and Technology, 2019, 53(10):1906-1917. (in Chinese)
[5] 李晓伟, 吴莘馨, 张作义, 等. 高温气冷堆示范工程螺旋管式直流蒸汽发生器工程验证试验[J]. 清华大学学报(自然科学版), 2021, 61(4):329-337. LI X W, WU X X, ZHANG Z Y, et al. Engineering test of HTR-PM helical tube once through steam generator[J]. Journal of Tsinghua University (Science & Technology), 2021, 61(4):329-337. (in Chinese)
[6] BOURE J A, BERGLES A E, TONG L S. Review of two-phase flow instability[J]. Nuclear Engineering and Design, 1973, 25(2):165-192.
[7] 张作义. 两相流不稳定性的能量原理[J]. 核科学与工程, 1989, 9(2):104-111. ZHANG Z Y. An energy principle in two phase flow instability[J]. Chinese Journal of Nuclear Science and Engineering, 1989, 9(2):104-111. (in Chinese)
[8] 张作义, 高祖瑛, 王大中. 两相流密度波不稳定性分析的一个显式判据[J]. 科学通报, 1990, 35(2):146-148. ZHANG Z Y, GAO Z Y, WANG D Z. An explicit criterion for analysing twophase flow density wave instability[J]. Chinese Science Bulletin, 1990, 35(13):1129-1133. (in Chinese)
[9] CHEN L, ZHANG X R, DENG B L. Near-critical natural circulation flows inside an experimental loop:Stability map and heat transfer[J]. Heat Transfer Engineering, 2016, 37(3-4):302-313.
[10] KAKAC S, BON B. A review of two-phase flow dynamic instabilities in tube boiling systems[J]. International Journal of Heat and Mass Transfer, 2008, 51(3-4):399-433.
[11] RUSPINI L C, MARCEL C P, CLAUSSE A. Two-phase flow instabilities:A review[J]. International Journal of Heat and Mass Transfer, 2014, 71:521-548.
[12] O'NEILL L E, MUDAWAR I. Review of two-phase flow instabilities in macro- and micro-channel systems[J]. International Journal of Heat and Mass Transfer, 2020, 157:119738.
[13] LI C, FANG X D, DAI Q M. Two-phase flow boiling instabilities:A review[J]. Annals of Nuclear Energy, 2022, 173:109099.
[14] PAPINI D, CAMMI A, COLOMBO M, et al. Time-domain linear and non-linear studies on density wave oscillations[J]. Chemical Engineering Science, 2012, 81:118-139.
[15] DONG R T, NIU F L, ZHOU Y, et al. Modeling analyses of two-phase flow instabilities for straight and helical tubes in nuclear power plants[J]. Nuclear Engineering and Design, 2016, 307:205-217.
[16] HOU S X, ZHAO F Y, TAI Y, et al. Analysis of flow instability for OTSG using frequency domain control theory[J]. Nuclear Technology, 2010, 169(2):126-133.
[17] NIU F L, TIAN L, YU Y, et al. Studies on flow instability of helical tube steam generator with Nyquist criterion[J]. Nuclear Engineering and Design, 2014, 266:63-69.
[18] ZHANG Y F, LI H X, LI L X, et al. Study on two-phase flow instabilities in internally-ribbed tubes by using frequency domain method[J]. Applied Thermal Engineering, 2014, 65(1-2):1-13.
[19] TANG Y, ZHOU Z W, ZHANG D B. Investigation of density wave instability in once-through superheated steam generators using SIGHT[J]. Annals of Nuclear Energy, 2017, 109:41-51.
[20] MA Y, LI X W, WU X X. Thermal-hydraulic characteristics and flow instability analysis of an HTGR helical tube steam generator[J]. Annals of Nuclear Energy, 2014, 73:484-495.
[21] LI Z Y, GAO P Z, LIN Y Q, et al. Investigation on flow instability in a natural circulation loop with rod bundles[J]. Annals of Nuclear Energy, 2019, 132:212-226.
[22] COLOMBO M, CAMMI A, PAPINI D, et al. RELAP5/MOD3.3 study on density wave instabilities in single channel and two parallel channels[J]. Progress in Nuclear Energy, 2012, 56:15-23.
[23] AMBROSINI W, FERRERI J C. Analysis of basic phenomena in boiling channel instabilities with different flow models and numerical schemes[C]//Proceedings of the 14th International Conference on Nuclear Engineering. Miami, USA:ICONE, 2006:889-900.
[24] AMBROSINI W. On the analogies in the dynamic behaviour of heated channels with boiling and supercritical fluids[J]. Nuclear Engineering and Design, 2007, 237(11):1164-1174.
[25] SHARMA S L, BUCHANAN J R, BERTODANO M A L D. Density wave instability verification of CFD two-fluid model[J]. Nuclear Science and Engineering, 2020, 194(8-9):665-675.
[26] PAPINI D, COLOMBO M, CAMMI A, et al. Experimental and theoretical studies on density wave instabilities in helically coiled tubes[J]. International Journal of Heat and Mass Transfer, 2014, 68:343-356.
[27] SAHA P. Thermally induced two-phase flow instabilities, including the effect of thermal non-equilibrium between the phases[D]. Atlanta:Georgia Institute of Technology, 1974.
[28] TAKITANI K, TAKEMURA T. Density wave instability in once-through boiling flow system, (I)[J]. Journal of Nuclear Science and Technology, 1978, 15(5):355-364.
[29] OZAWA M, NAKANISHI S, ISHIGAI S, et al. Flow instabilities in boiling channels:Part 2 geysering[J]. Bulletin of JSME, 1979, 22(170):1119-1126.
[30] 姜胜耀, 吴莘馨, 张佑杰. 闪蒸引起的密度波振荡[J]. 中国核科技报告, 1997(S1):65. JIANG S Y, WU X X, ZHANG Y J. Flashing coupled density wave oscillation[J]. China Nuclear Science and Technology Report, 1997(S1):65. (in Chinese)
[31] 吴莘馨, 姜胜耀, 吴少融, 等. 喷泉不稳定诱发间歇流量振荡实验研究[J]. 核动力工程, 1997, 18(2):124-128, 139. WU X X, JIANG S Y, WU S R, et al. Experimental investigation on geysering induced intermittent flow oscillation[J]. Nuclear Power Engineering, 1997, 18(2):124-128, 139. (in Chinese)
[32] JIANG S Y, WU X X, ZHANG Y J. Experimental study of two-phase flow oscillation in natural circulation[J]. Nuclear Science and Engineering, 2000, 135(2):177-189.
[33] PENG S J, PODOWSKI M Z, LAHEY R T, et al. NUFREQ-NP:A computer code for the stability analysis of boiling water nuclear reactors[J]. Nuclear Science and Engineering, 1984, 88(3):404-411.
[34] LAHEY JR R T, PODOWSKI M Z. On the analysis of various instabilities in two-phase flows[J]. Multiphase Science and Technology, 1989, 4(1-4):183-370.
[35] PARK G C, PODOWSKI M Z, BECKER M, et al. The development of a closed-form analytical model for the stability analysis of nuclear-coupled density-wave oscillations in boiling water nuclear reactors[J]. Nuclear Engineering and Design, 1986, 92(2):253-281.
[36] 吕俊复, 吴玉新, 李舟航, 等. 气液两相流动与沸腾传热[M]. 北京:科学出版社, 2017. LV J F, WU Y X, LI Z H, et al. Gas-liquid two-phase flow and boiling heat transfer[M]. Beijing:Science Press, 2017. (in Chinese)
[37] 朱宏晔, 居怀明, 段日强, 等. 高温气冷堆螺旋管直流蒸汽发生器时域模型[J]. 清华大学学报(自然科学版), 2012, 52(2):238-242. ZHU H Y, JV H M, DUAN R Q, et al. Time domain model for once-through helical coil steam generator for high-temperature gas-cooled reactors[J]. Journal of Tsinghua University (Science & Technology), 2012, 52(2):238-242. (in Chinese)
[38] LIU J L, LI H X, LEI X L, et al. Numerical study on the effect of pipe wall heat storage on density wave instability of supercritical water[J]. Nuclear Engineering and Design, 2018, 335:106-115.
[39] LIU J L, LI H X, ZHANG Q, et al. Numerical study on the density wave oscillation of supercritical water in parallel multichannel system[J]. Nuclear Engineering and Design, 2019, 342:10-19.
[40] LIU J L, LI H X, LEI X L, et al. Numerical study on the effect of dissymmetry heating on flow instability of supercritical water in two parallel channels[J]. Annals of Nuclear Energy, 2020, 144:107586.
[41] WANG W Y, YANG D, DONG L, et al. Experimental and numerical study on density wave oscillations of supercritical water in parallel water wall channels of an ultra-supercritical circulating fluidized bed boiler[J]. Applied Thermal Engineering, 2020, 165:114584.
[42] HENNIG D, LANGE C, RIZWAN-UDDIN, et al. Principles for the application of bifurcation theory for the systematic analysis of nuclear reactor stability, Part1:Theory[J]. Progress in Nuclear Energy, 2019, 115:231-249.
[43] PANDEY V, SINGH S. Bifurcation analysis of density wave oscillations in natural circulation loop[J]. International Journal of Thermal Sciences, 2017, 120:446-458.
[44] VORA R, CHAKRABORTY A, SINGH S. Bifurcation analysis of out-of-phase oscillations in boiling water reactors using multipoint neutron kinetics[J]. Progress in Nuclear Energy, 2020, 120:103218.
[45] RAHMAN E, SINGH S. Non-linear stability analysis of pressure drop oscillations in a heated channel[J]. Chemical Engineering Science, 2018, 192:176-186.
[46] HENNIG D, RIZWAN-UDDIN, LANGE C, et al. Principles for the application of bifurcation theory for the systematic analysis of nuclear reactor stability, Part2:Application[J]. Progress in Nuclear Energy, 2019, 113:263-280.
[47] 刘峰, 杨竹强, 张博, 等. 基于吸引域边界的流量漂移失稳动力学机理研究[J]. 核动力工程, 2021, 42(S1):70-76. LIU F, YANG Z Q, ZHANG B, et al. Investigation on dynamic mechanism of flow excursion instability based on boundary of attraction domain[J]. Nuclear Power Engineering, 2021, 42(S1):70-76. (in Chinese)
[48] MISHRA A M, SINGH S. Subcritical and supercritical bifurcations for two-phase flow in a uniformly heated channel with different inclinations[J]. International Journal of Heat and Mass Transfer, 2016, 93:235-249.
[49] TAKITANI K. Density wave instability in once-through boiling flow system, (II)[J]. Journal of Nuclear Science and Technology, 1978, 15(6):389-399.
[50] SU Y, LI X W, WU X X. Theoretical analysis of Ledinegg instability and density wave oscillation using dimensionless numbers[J]. Applied Thermal Engineering, 2022, 201:117805.
[51] ZHANG Y F, LI H X, LI L X, et al. A new model for studying the density wave instabilities of supercritical water flows in tubes[J]. Applied Thermal Engineering, 2015, 75:397-409.
[52] LIANG Q, LI X W, SU Y, et al. Frequency domain analysis of two-phase flow instabilities in a helical tube once through steam generator for HTGR[J]. Applied Thermal Engineering, 2020, 168:114839.
[53] 杨瑞昌, 鲁钟琪, 施德强, 等. 并联螺旋蒸发管内汽液两相流动不稳定性的模化试验研究[J]. 工程热物理学报, 1994, 15(1):84-88. YANG R C, LU Z Q, SHI D Q, et al. Modeling experimental study of two-phase flow instability in parallel coiled evaporating tubes[J]. Journal of Engineering Thermophysics, 1994, 15(1):84-88. (in Chinese)
[54] VNAL H C. Some aspects of two-phase flow, heat transfer and dynamic instabilities in medium and high pressure steam generators[D]. Delft:Delft University of Technology, 1981.
[55] FRANCE D M, CARLSON R D, ROY R P. Measurement and analysis of dynamic instabilities in fluid-heated two-phase flow[J]. International Journal of Heat and Mass Transfer, 1986, 29(12):1919-1929.
[56] 杨冬, 聂超, 周科, 等. 超临界机组深度调峰工质流动不稳定试验与理论计算研究[J/OL]. 洁净煤技术.(2022-12-28)[2023-01-14]. https://kns.cnki.net/kcms/detail//11.3676.TD.20221227.1532.005.html. YANG D, NIE C, ZHOU K, et al. Study on experimental research and theoretical calculation of flow instability in deep peak-shaving of supercritical units[J/OL].Clean Coal Technology. (2022-12-28)[2023-01-14]. https://kns.cnki.net/kcms/detail//11.3676.TD.20221227.1532.005.html. (in Chinese)
[57] KHABENSKY V B, GERLIGA V A. Coolant flow instabilities in power equipment[M]. Boca Raton:CRC Press, 2013.
[58] KHABENSKII V B, KVETNYL M A. Simplified formulae for evaluating the boundary of oscillatory thermohydraulic instability in a two phase flow[J]. Thermal Engineering, 1988, 35(4):208-212.
[59] SU Y, LI X W, LI Z L, et al. Comparison analysis of density wave oscillation type two-phase flow instability of superheated and saturated boiling tubes[J]. Annals of Nuclear Energy, 2023, 182:109626.
[60] LEDINEGG M. Instability of flow during natural and forced circulation[J]. Die Waerme, 1938, 61(8):891-898.
[61] YANG K, ZHANG A, WANG J B. On the Ledinegg instability in parallel channels:A new and exact criterion[J]. International Journal of Thermal Sciences, 2018, 129:193-200.
[62] LI X W, GAO W K, SU Y, et al. Thermal analysis of HTGR helical tube once through steam generators using 1D and 2D methods[J]. Nuclear Engineering and Design, 2019, 355:110352.
[63] 范弘毅, 李晓伟, 吴莘馨, 等. 高温气冷堆螺旋管式超临界蒸汽发生器热工水力程序开发及分析[J]. 原子能科学技术, 2022, 56(11):2343-2353. FAN H Y, LI X W, WU X X, et al. Thermal-hydraulic code development and analysis of HTGR helical tube supercritical steam generator[J]. Atomic Energy Science and Technology, 2022, 56(11):2343-2353. (in Chinese)
[64] JU H M, XU Y H, HUANG Z Y, et al. Research method and two-phase flow stability of the steam generator of HTR-10[J]. Journal of Nuclear Science and Technology, 2001, 38(9):739-744.
[65] 朱宏晔, 杨星团, 居怀明, 等. 高温气冷堆螺旋管蒸汽发生器流量漂移不稳定性研究[J]. 核动力工程, 2012, 33(4):76-80. ZHU H Y, YANG X T, JV H M, et al. Analysis of flow excursion instabilities in helically coiled tube steam generator of high temperature gas-cooled reactor[J]. Nuclear Power Engineering, 2012, 33(4):76-80. (in Chinese)
[66] 杨瑞昌, 覃世伟, 刘若雷. 自然循环蒸汽发生器倒U型管内单相水流动及传热特性分析[J]. 工程热物理学报, 2006, 27(1):130-132. YANG R C, QIN S W, LIU R L. Investigation on water flow and heat transfer in U-tubes of steam generator with natural circulation[J]. Journal of Engineering Thermophysics, 2006, 27(1):130-132. (in Chinese)
[67] 杨瑞昌, 刘京宫, 黄彦平, 等. 自然循环蒸汽发生器倒U型管内的倒流计算[J]. 核动力工程, 2010, 31(1):57-60. YANG R C, LIU J G, HUANG Y P, et al. Calculation of reverse flow in inverted U-tubes of steam generator during natural circulation[J]. Nuclear Power Engineering, 2010, 31(1):57-60. (in Chinese)
[68] 姜胜耀, 张佑杰, 吴莘馨. 自然循环静态流动不稳定研究[J]. 核动力工程, 2000, 21(3):243-247, 288. JIANG S Y, ZHANG Y J, WU X X. Static flow instability in natural circulation[J]. Nuclear Power Engineering, 2000, 21(3):243-247, 288. (in Chinese)
[69] 姜胜耀, 张佑杰, 吴莘馨. 自然循环静态流量漂移诱发动态流量振荡研究[J]. 清华大学学报(自然科学版), 2000, 40(2):63-66. JIANG S Y, ZHANG Y J, WU X X. Static flow instability induced dynamic flow oscillation in natural circulation[J]. Journal of Tsinghua University (Science & Technology), 2000, 40(2):63-66. (in Chinese)
[70] ISHII M. Thermally induced flow instabilities in two-phase mixtures in thermal equilibrium[D]. Atlanta:Georgia Institute of Technology, 1971.
[71] ACHARD J L, DREW D A, LAHEY R T J R. The effect of gravity and friction on the stability of boiling flow in a channel[J]. Chemical Engineering Communications, 1981, 11(1-3):59-79.
[72] DELMASTRO D F, CLAUSSE A, CONVERTI J. The influence of gravity on the stability of boiling flows[J]. Nuclear Engineering and Design, 1991, 127(1):129-139.
[73] BAIKIN M, TAITEL Y, BARNEA D. Flow rate distribution in parallel heated pipes[J]. International Journal of Heat and Mass Transfer, 2011, 54(19-20):4448-4457.
[74] LIU F, LV J S, ZHANG B, et al. Nonlinear stability analysis of Ledinegg instability under constant external driving force[J]. Chemical Engineering Science, 2019, 206:432-445.
[75] LIU F, YANG Z Q, ZHANG B, et al. Study on Ledinegg instability of two-phase boiling flow with bifurcation analysis and experimental verification[J]. International Journal of Heat and Mass Transfer, 2020, 147:118954.
[76] LIU F, ZHANG B, YANG Z Q. Lyapunov stability and numerical analysis of excursive instability for forced two-phase boiling flow in a horizontal channel[J]. Applied Thermal Engineering, 2019, 159:113664.
[77] FUKUDA K, KOBORI T. Classification of two-phase flow instability by density wave oscillation model[J]. Journal of Nuclear Science and Technology, 1979, 16(2):95-108.
[78] MASINI G, POSSA G, TACCONI F A. Flow instability thresholds in parallel heated channels[J]. Energia Nucleare, 1968, 15(12):773-782.
[79] SU Y, LI X W, LI Z L, et al. Theoretical analysis of the flow stability of HTGR supercritical steam generators using dimensionless numbers[J]. Nuclear Engineering and Design, 2022, 394:111820.
[80] WANG X Y, TIAN W X, HUANG S Y, et al. Theoretical investigation of two-phase flow instability between parallel channels of natural circulation in rolling motion[J]. Nuclear Engineering and Design, 2019, 343:257-268.
[81] YUN G, QIU S Z, SU G H, et al. Theoretical investigations on two-phase flow instability in parallel multichannel system[J]. Annals of Nuclear Energy, 2008, 35(4):665-676.
[82] 苏阳, 李晓伟, 吴莘馨. 基于变管径模型的高温气冷堆螺旋管式直流蒸发器两相流稳定性影响参数分析[J]. 原子能科学技术, 2022, 56(12):2747-2756. SU Y, LI X W, WU X X. Parameter analysis of two-phase flow stability in HTGR helical tube once through steam generator based on variable tube diameter model[J]. Atomic Energy Science and Technology, 2022, 56(12):2747-2756. (in Chinese)
[83] 苏阳, 李晓伟, 阎慧杰, 等. 物理模型及边界条件对直流蒸发管两相流不稳定性边界影响研究[J]. 原子能科学技术, 2019, 53(4):624-631. SU Y, LI X W, YAN H J, et al. Influence of physical model and boundary condition on two-phase flow instability boundary in once-through evaporation tube[J]. Atomic Energy Science and Technology, 2019, 53(4):624-631. (in Chinese)
[84] 付文, 李晓伟, 吴莘馨, 等. 并联直流蒸发管内两相流密度波不稳定性研究[J]. 工程热物理学报, 2014, 35(3):576-580. FU W, LI X W, WU X X, et al. Investigation on two-phase flow density wave instability in parallel once-through evaporation tubes[J]. Journal of Engineering Thermophysics, 2014, 35(3):576-580. (in Chinese)
[85] 辛亚飞, 聂超, 毕凌峰, 等. 倾斜管内汽水两相流动不稳定特性的数值分析[J]. 电力科技与环保, 2022, 38(3):195-201. XIN Y F, NIE C, BI L F, et al. Numerical analysis of unstable characteristics of steam-water two-phase flow in inclined pipe[J]. Electric Power Technology and Environmental Protection, 2022, 38(3):195-201. (in Chinese)
[86] 李会雄, 汪斌, 陈听宽. 垂直并联多通道内高温高压汽水两相流密度波型不稳定性的实验研究[J]. 中国动力工程学报, 2005, 25(1):55-59, 77. LI H X, WANG B, CHEN T K. Experimental research on pulsating density instability of high-temperature and high-pressure steam-water two-phase flow[J]. Chinese Journal of Power Engineering, 2005, 25(1):55-59, 77. (in Chinese)
[87] XIA G L, PENG M J, GUO Y. Research of two-phase flow instability in parallel narrow multi-channel system[J]. Annals of Nuclear Energy, 2012, 48:1-16.
[88] GUO Y, HUANG J, XIA G L, et al. Experiment investigation on two-phase flow instability in a parallel twin-channel system[J]. Annals of Nuclear Energy, 2010, 37(10):1281-1289.
[89] LEE J D, PAN C. Dynamics of multiple parallel boiling channel systems with forced flows[J]. Nuclear Engineering and Design, 1999, 192(1):31-44.
[90] BAKHSHAN Y, KAZEMI S. Numerical simulation of external inertia and compressibility effects on the dynamic instabilities of two-phase boiling flows in horizontal parallel channels[J]. Annals of Nuclear Energy, 2018, 113:294-307.
[91] MAULBETSCH J S, GRIFFITH P. System-induced instabilities in forced-convection flows with subcooled boiling[C]//Proceedings of the 3rd International Heat Transfer Conference. Chicago, USA:AICE, 1966:247-257.
[92] RUSPINI L C. Experimental and numerical investigation on two-phase flow instabilities[D]. Trondheim:Norwegian University, 2013.
[93] MANAVELA C E, FERNANDINO M, DORAOC A. Review on pressure drop oscillations in boiling systems[J]. Nuclear Engineering and Design, 2012, 250:436-447.
[94] JU H M, YU Y, HUANG Z Y, et al. Experiment and verification test of the once-through steam generator of the 10 MW high-temperature gas-cooled reactor flow stability of the once-through steam generator[J]. Journal of Nuclear Science and Technology, 2004, 41(4):524-528.
[95] LI R Z, JU H M. Structural design and two-phase flow stability test for the steam generator[J]. Nuclear Engineering and Design, 2002, 218(1-3):179-187.
[96] 李晓伟. HTR-PM蒸汽发生器两相流稳定性分析报告[R]. 北京:清华大学核能与新能源技术研究院, 2018. LI X W. Two-phase flow instability analysis of the HTR-PM once through steam generator[R]. Beijing:Institute of Nuclear and New Energy Technology, Tsinghua University, 2018. (in Chinese)
[97] 李晓伟. 高温气冷堆蒸汽发生器工程验证试验报告[R]. 北京:清华大学核能与新能源技术研究院, 2019. LI X W. Experimental report for HTR-PM helical tube once through steam generator[R]. Beijing:Institute of Nuclear and New Energy Technology, Tsinghua University, 2019. (in Chinese)

基金

国家重点研发计划资助项目（2020YFB1901600）；国家科技重大专项资助项目（ZX06901）

PDF(6631 KB)

Accesses

Citation

Detail

段落导航

收稿日期	出版日期
2023-01-14	2023-08-15
发布日期
2023-07-22

选择文件类型/文献管理软件名称

选择包含的内容

摘要

Abstract

关键词

Key words

引用本文

{{custom_sec.title}}

{{custom_sec.title}}

参考文献

基金

访问统计

模态框（Modal）标题

选择文件类型/文献管理软件名称

选择包含的内容

摘要

Abstract

关键词

Key words

引用本文

{{custom_sec.title}}

{{custom_sec.title}}

参考文献

基金

访问统计