Advance Search
Volume 46 Issue 4
Aug.  2025
Turn off MathJax
Article Contents
Shen Teng, Wang Chengyu, Guo Shaoqiang, He Kai. Study on Oxidation Corrosion of Nuclear Graphite by Water Vapor[J]. Nuclear Power Engineering, 2025, 46(4): 152-158. doi: 10.13832/j.jnpe.2024.090008
Citation: Shen Teng, Wang Chengyu, Guo Shaoqiang, He Kai. Study on Oxidation Corrosion of Nuclear Graphite by Water Vapor[J]. Nuclear Power Engineering, 2025, 46(4): 152-158. doi: 10.13832/j.jnpe.2024.090008

Study on Oxidation Corrosion of Nuclear Graphite by Water Vapor

doi: 10.13832/j.jnpe.2024.090008
  • Received Date: 2024-09-09
  • Rev Recd Date: 2024-11-04
  • Publish Date: 2025-08-15
  • In order to study the oxidation reaction properties of nuclear graphite by water vapor and establish the graphite-water vapor corrosion reaction model based on classical Langmuir-Hinshelwood (L-H) model, we conducted the experiments on the oxidation corrosion of graphite by water vapor based on gas concentration method. The experiment results demonstrated that CO2 was generated at the temperature higher than 950℃ or 1000℃ in the experimental condition of the helium and water vapor mixed gas flow rate of 10 L/min and the water vapo concentration of 3% to 10%, and the mixture added with 1% H2 has no obviously influence on reaction rate, which had obviously difference with classical L-H model. As a result, new reaction model was established based on the experiment results, which added the oxidation reaction of graphite by water vapor generating CO2 and H2 and removed the H2 partial pressure term in L-H model. The experiment data was used to build a new model and verify the model respectively. The study results demonstrated that the new model was suitable for the simulation of oxidation of graphite by water vapor at a relative high water vapor concentration, which could relatively accurately analyze and calculate the corrosion rate and gas generating rate.

     

  • loading
  • [1]
    徐世江,康飞宇. 《核工程中的炭和石墨材料》[M]. 北京:清华大学出版社,2010:252-294.
    [2]
    ALONSO G, RAMIREZ R, DEL VALLE E, et al. Process heat cogeneration using a high temperature reactor[J]. Nuclear Engineering and Design, 2014, 280: 137-143. doi: 10.1016/j.nucengdes.2014.10.005
    [3]
    FANG C, MORRIS R, LI F. Safety features of high temperature gas cooled reactor[J]. Science and Technology of Nuclear Installations, 2017, 2017: 1-3.
    [4]
    AZEVEDO C R F. Selection of fuel cladding material for nuclear fission reactors[J]. Engineering Failure Analysis, 2011, 18(8): 1943-1962. doi: 10.1016/j.engfailanal.2011.06.010
    [5]
    CONTESCU C I, MEE R W. Status of chronic oxidation studies of graphite:ORNL/TM-2016/195[R]. Tennessee: Oak Ridge National Laboratory, 2016.
    [6]
    WANG Y, ZHENG Y H, LI F, et al. Analysis on blow-down transient in water ingress accident of high temperature gas-cooled reactor[J]. Nuclear Engineering and Design, 2014, 271: 404-410. doi: 10.1016/j.nucengdes.2013.12.009
    [7]
    WANG C Q, SHI S B, ARCILESI D, et al. Scaling analysis and test facility design for steam ingress accident in MHTGR[C]//Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety. Gyeongju: Korean Nuclear Society, 2016.
    [8]
    CHO Y J, GARCIA D, YU H Z, et al. Oxidation behaviors of matrix-grade graphite during water vapor ingress accidents for high temperature gas-cooled reactors[J]. Carbon, 2021, 185: 161-176. doi: 10.1016/j.carbon.2021.09.032
    [9]
    CHO Y J, LU K. Water vapor oxidation of SiC layer in surrogate TRISO fuel particles[J]. Composites Part B: Engineering, 2021, 215: 108807. doi: 10.1016/j.compositesb.2021.108807
    [10]
    CHO Y J, LU K. Water vapor oxidation behaviors of nuclear graphite IG-110 for a postulated accident scenario in high temperature gas-cooled reactors[J]. Carbon, 2020, 164: 251-260. doi: 10.1016/j.carbon.2020.04.004
    [11]
    WICHNER R P, BURCHELL T D, CONTESCU C I. Penetration depth and transient oxidation of graphite by oxygen and water vapor[J]. Journal of Nuclear Materials, 2009, 393(3): 518-521. doi: 10.1016/j.jnucmat.2009.06.032
    [12]
    CONTESCU C I, MEE R W, LEE Y J J et al. Beyond the classical kinetic model for chronic graphite oxidation by moisture in high temperature gas-cooled reactors[J]. Carbon, 2018, 127: 158-169. doi: 10.1016/j.carbon.2017.11.001
    [13]
    VELASQUEZ C, HIGHTOWER G, BURNETTE R. The oxidation of H-451 graphite by steam. Part I: reaction kinetics:GA-A14951[R]. Oakland: General Atomic Co. , 1978: 1-62.
    [14]
    WANG C Q, SUN X D, CHRISTENSEN R N. Multiphysics simulation of moisture-graphite oxidation in MHTGR[J]. Annals of Nuclear Energy, 2019, 131: 483-495. doi: 10.1016/j.anucene.2019.03.040
    [15]
    HINSSEN H K, KÜHN K, MOORMANN R, et al. Oxidation experiments and theoretical examinations on graphite materials relevant for the PBMR[J]. Nuclear Engineering and Design, 2008, 238(11): 3018-3025. doi: 10.1016/j.nucengdes.2008.02.013
  • 加载中

Catalog

    通讯作者: 陈斌, bchen63@163.com
    • 1. 

      沈阳化工大学材料科学与工程学院 沈阳 110142

    1. 本站搜索
    2. 百度学术搜索
    3. 万方数据库搜索
    4. CNKI搜索

    Figures(10)  / Tables(3)

    Article Metrics

    Article views (19) PDF downloads(0) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return