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Evaluation of thermophoretic effects on graphite dust coagulation in high-temperature gas-cooled reactors 被引量:1

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摘要 In high-temperature gas-cooled reactors,graphite dust particles within the reactor core and the heat transfer equipment experience large temperature gradients.Under such conditions,thermophoresis may play an important role in determining aerosol evolution.This study presents a theoretical and numerical analysis of the thermophoretic effects on aerosol coagulation within these reactors.The coagulation rates for Brownian versus thermophoretic coagulation are calculated and compared for various temperature gradients.Our results show that thermophoretic coagulation dominates over Brownian coagulation for large temperature gradients.We defined an enhancement factor to evaluate the role of thermophoretic coagulation under various reactor conditions.The enhancement factor increased dramatically with increasing temperature gradient,decreasing pressure and increasing particle diameter,but was not very sensitive to temperature change.The time evolution of the particle size distribution related to combined Brownian and thermophoretic coagulation was simulated using a log-skew-normal method of moments.The simulation results indicate that aerosol evolution can be strongly accelerated by thermophoretic coagulation under large temperature gradients.
出处 《Particuology》 SCIE EI CAS CSCD 2020年第4期45-52,共8页 颗粒学报(英文版)
基金 This work was supported by the National Natural Science Foundation of China(Grant No.51676112) the National Key Research&Development Program of China(Grant No.2016YFC0202700) the National Science&Technology Major Project(Grant No.ZX069) Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education.We also thank Prof.David Christopher for editing the English.
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  • 1雒晓卫,于溯源,张振声,何树延.HTR-10产生石墨粉尘量的估算及其尺寸分布[J].核动力工程,2005,26(2):203-208. 被引量:22
  • 2Association of German Engineers (VDI),The Society for Energy Technologies(PUBL).AVR-experimental high-temperature reactor,21 years of successful operation for a future energy technology[M].Düsseldorf:Verlag des Vereins Deutscher Ingenieure,1990.
  • 3LUO Xiaowei,ZHANG Lihong,YU Suyuan.The wear properties of nuclear grade graphite IG-11 under different loads[J].International Journal of Nuclear Energy Science and Techno-logy,2004,1:33-43.
  • 4雒晓卫 于溯源 盛选禹.不同气氛下石墨IG—11磨损性能研究[J].摩擦学学报,.
  • 5FRIEDLANDER S K,WANG C S.Self-pre-serving particle size distribution for coagulation by Brownian motion[J].J Colloid Interface Sci,1966,22:126-132.
  • 6WU Zongxin,LIN Dengcai,ZHONG Daxin.The design features of the HTR-10[J].Nuclear Engineering and Design,2002,218:25-32.
  • 7FRIEDLANDER S K.Smoke,dust and haze:Fundamentals of aerosol behavior[M].USA:John Wiley & Sons,Inc,1977:267-275.
  • 8LANDGREBE J D,PRATSINIS S E.A discrete-sectional model for particulate production by gas-phase chemical reaction and aerosol coagulation in the free-molecular regime[J].Journal of Colloid and Interface Science,1990,139:63-86.
  • 9VEMURY S,KUSTERS K A,PRATSINIS S E.Time-lag for attainment of the self-pre-serving particle size distribution by coagulation[J].Journal of Colloid Interface Science,1994,165(1):53-59.
  • 10于溯源,华宏亮.HTR-10氦气流中石墨颗粒尺寸的估计[J].核动力工程,2001,22(5):410-413. 被引量:5

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