Graphite dust deposition in the HTR-10 steam generator

被引:1
作者
Wei Peng [1 ]
Yanan Zhen [1 ]
Xiaoyong Yang [1 ]
Suyuan Yu [1 ]
机构
[1] Institute of Nuclear and New Energy Technology of Tsinghua University,The Key Laboratory of Advanced Reactor Engineering and Safety,Ministry of Education
关键词
Graphite dust; High-temperature gas-cooled reactor; Steam generator; Deposition;
D O I
暂无
中图分类号
TL353.13 [];
学科分类号
082701 ;
摘要
Graphite dust has an important effect on the safe operation of a high-temperature gas-cooled reactor(HTR).The present study analyzes temperature and flow field distributions in the HTR-10 steam generator.The temperature and flow field distributions are then used to study thermophoretic deposition and turbulent deposition.The results show that as the dust diameter increases,the thermophoretic deposition decreases,while the turbulent deposition first decreases and then increases.The thermophoretic deposition is higher at higher reactor powers,with turbulent deposition growing more rapidly at higher reactor power.For small particles,the thermophoretic deposition effect is greater than the turbulent deposition effect,while for large particles,the turbulent deposition effect is dominant.
引用
收藏
页码:533 / 539
页数:7
相关论文
共 10 条
  • [1] HTR-10产生石墨粉尘量的估算及其尺寸分布
    雒晓卫
    于溯源
    张振声
    何树延
    不详
    [J]. 核动力工程 , 2005, (02) : 203 - 208
  • [2] GENERATION OF GRAPHITE PARTICLES BY ROTATIONAL/SPINNING ABRASION AND THEIR CHARACTERIZATION
    Troy, Raymond S.
    Tompson, Robert V.
    Ghosh, Tushar K.
    Loyalka, Sudarshan K.
    [J]. NUCLEAR TECHNOLOGY, 2012, 178 (03) : 241 - 257
  • [3] Computational prediction of dust production in pebble bed reactors[J] . Maziar Rostamian,Gabriel P. Potirniche,Joshua J. Cogliati,Abderrafi Ougouag,Akira Tokuhiro.Nuclear Engineering and Design . 2011
  • [4] A review of radionuclide behaviour in the primary system of a very-high-temperature reactor
    Kissane, M. P.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2009, 239 (12) : 3076 - 3091
  • [5] Fission Product Transport and Source Terms in HTRs: Experiencefrom AVR Pebble Bed Reactor[J] . Rainer Moormann,Michel Giot.Science and Technology of Nuclear Installations . 2008
  • [6] Temperature effect on IG-11 graphite wear performance
    Luo, XW
    Yu, SY
    Sheng, XY
    He, SY
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2005, 235 (21) : 2261 - 2274
  • [7] The wear properties of nuclear grade graphite IG-11 under different loads[J] . Xiaowei Luo,Lihong,Zhang,Suyuan,Yu.Int. J. of Nuclear Energy Science and Technology . 2004 (1)
  • [8] SLIP CORRECTION MEASUREMENTS OF SPHERICAL SOLID AEROSOL-PARTICLES IN AN IMPROVED MILLIKAN APPARATUS
    ALLEN, MD
    RAABE, OG
    [J]. AEROSOL SCIENCE AND TECHNOLOGY, 1985, 4 (03) : 269 - 286
  • [9] Aerosol measurement:Principles,techniques,and applications .2 Brockmann,J.E. Van Nostrand Reinhold . 1993
  • [10] Fuel performance and fission product be-haviour in gas-cooled reactors .2 IAEA. IAEA-TECDOC-978 . 1997