Volume 33 Issue 3
Mar.  2021
Turn off MathJax
Article Contents
Zhou Xiaokai, Tong Lili. Numerical simulation and experimental verification on the diffusion behavior of tritium in zirconium alloy cladding materials[J]. High Power Laser and Particle Beams, 2021, 33: 036001. doi: 10.11884/HPLPB202133.200275
Citation: Zhou Xiaokai, Tong Lili. Numerical simulation and experimental verification on the diffusion behavior of tritium in zirconium alloy cladding materials[J]. High Power Laser and Particle Beams, 2021, 33: 036001. doi: 10.11884/HPLPB202133.200275

Numerical simulation and experimental verification on the diffusion behavior of tritium in zirconium alloy cladding materials

doi: 10.11884/HPLPB202133.200275
  • Received Date: 2020-09-20
  • Rev Recd Date: 2020-11-19
  • Available Online: 2021-03-30
  • Publish Date: 2021-03-05
  • The research on the diffusion behavior of tritium in zirconium alloy is a crucial problem for nuclear power plant radiation safety evaluation. Based on the basic model of tritium diffusion, a one-dimensional simulation program for the behavior of tritium diffusion was established in this work. The simulation program was verified by typical experiments, and the simulation results were in good agreement with the experimental results. The effects of different concentration and temperature distribution of tritium on the diffusion behavior of tritium in zirconium alloy cladding materials were analyzed. The results show that the increase of tritium concentration in P-C gap lead to the increase of tritium diffusion flux and permeability flux in and out of cladding. Due to the relatively low diffusion coefficient of the coated oxide layer, the existence of the coated oxide layer limits the tritium permeability greatly. The effect of temperature on the diffusion rate of tritium is exponential. The higher the temperature is, the faster the diffusion rate is. The relative low temperature of the oxide layer on the outer surface of zirconium alloy limits the rate of tritium permeation out of the cladding tube. Thermally induced diffusion due to temperature gradient is beneficial to limit the permeation flux of tritium diffusing out of the zirconium cladding.
  • loading
  • [1]
    陈海英, 张春明, 王韶伟. 压水堆3H源项计算分析[J]. 原子能科学技术, 2016, 50(2):459-463. (Chen Haiying, Zhang Chunming, Wang Shaowei. Calculation analysis of tritium source term in PWR[J]. Atomic Energy Science and Technology, 2016, 50(2): 459-463
    [2]
    GB 6249-2011. 核动力厂环境辐射防护规定[S].

    GB 6249-2011. Regulations for environmental radiation protection of nuclear power plant[S]
    [3]
    Kearns J J. Diffusion coefficient of hydrogen in alpha zirconium, zircaloy-2, zircaloy-4[J]. Journal of Nuclear Materials, 1972, 43: 330-338. doi: 10.1016/0022-3115(72)90065-7
    [4]
    Kunz W, Greger G U, Munzel H. Diffusion of tritium in zircaloy-2[J]. Journal of Nuclear Materials, 1980, 88: 15-22. doi: 10.1016/0022-3115(80)90381-5
    [5]
    Khatamian D. Diffusion of hydrogen in single crystals of monoclinic-ZrO2 and yttrium stabilized cubic zirconia[J]. Defect and Diffusion Forum, 2010, 297/301: 631-640. doi: 10.4028/www.scientific.net/DDF.297-301.631
    [6]
    Smith T. Kinetics and mechanism of hydrogen permeation of oxide films on zirconium[J]. Journal of Nuclear Materials, 1966, 18(3): 323-336. doi: 10.1016/0022-3115(66)90173-5
    [7]
    Hanson D L, Richards M B, Connors G P.TRIGO code description and user’s guide[R], GA-20128-911081, 2006.
    [8]
    Eung S K, Chang H O, Patterson M. Study on the tritium behaviors in the VHTR system. Part 1: Development of tritium analysis code for VHTR and verification[J]. Nuclear Engineering and Design, 2010, 240: 1758-1767. doi: 10.1016/j.nucengdes.2010.02.023
    [9]
    Longhurst G R. TMAP7 User Manual[R]. INL/EXT-04-02352, 2004.
    [10]
    Ohashi H, Sherman S. Tritium movement and accumulation in the NGNP system interface and hydrogen production[R]. INL/EXT-07-12746, 2007.
    [11]
    Yook D, Lee K J, Lee Y, et al. Estimation of the tritium behavior in the pebble type gas cooled reactor for hydrogen production[J]. Nuclear Science and Techniques, 2006, 43: 1522-1529. doi: 10.1080/18811248.2006.9711249
    [12]
    Aly A, Avramova M, Ivanov K, et al. Three dimensional fuel pin model validation by prediction of hydrogen distribution in cladding and comparison with experiment[R]. DOE-NEUP-13-5180, 2017.
    [13]
    Yamanaka S, Miyake M, Katsura M. Hydrogen solubility in zirconium alloys[J]. Journal of Nuclear Materials, 1995, 247(1/2): 315-321.
    [14]
    Park M Y, Kim B Y, Kim E S. Development of semi-empirical model for tritium permeation under non-uniform temperature distribution at heat exchanger tube wall[J]. Annals of Nuclear Energy, 2015, 75: 413-420. doi: 10.1016/j.anucene.2014.08.044
    [15]
    黎辉, 梅其良, 付亚茹. 核电厂氚的产生和排放分析[J]. 原子能科学技术, 2015, 49(4):739-743. (Li Hui, Mei Qiliang, Fu Yaru. Analysis of generation and release of tritium in nuclear power plant[J]. Atomic Energy Science and Technology, 2015, 49(4): 739-743 doi: 10.7538/yzk.2015.49.04.0739
    [16]
    Sawatzky A. The diffusion and solubility of hydrogen in the alpha-phase of zircaloy-2[J]. Journal of Nuclear Materials, 1960, 2(1): 62-68. doi: 10.1016/0022-3115(60)90025-8
    [17]
    Takagi I, Une K, Miyamura S, et al. Deuterium diffusion in steam-corroded oxide layer of zirconium alloys[J]. Journal of Nuclear Material, 2011, 419: 339-346. doi: 10.1016/j.jnucmat.2011.06.001
    [18]
    Robinson S M, Chattin M R, Giaquinto J M, et al. Evaluation of tritium content and release from pressurized water reactor fuel cladding[R]. ORNL/SPR-2015/425, 2015.
    [19]
    Barberis P, Frichet A. Characterization of zircaloy-4 oxide layers by impedance spectroscopy[J]. Journal of Nuclear Materials, 1999, 273: 182-191. doi: 10.1016/S0022-3115(99)00025-2
    [20]
    Kammenzind B F, Franklin D G, Peters H R, et al. Hydrogen pickup and redistribution in alpha-annealed zircaloy-4[C]//11th International Symp on Zr in the Nuclear Industry. 1996: 338-370.
  • 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(6)  / Tables(2)

    Article views (1083) PDF downloads(64) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return