NUCLEAR TECHNIQUES, Volume. 47, Issue 9, 090601(2024)

Development and validation of models for fuel rod oxidation and hydrogen pick-up behaviors in pressurized water reactor

Nan CHEN... Fengrui XIANG, Yanan HE*, Yingwei WU, Jing ZHANG, Guanghui SU, Wenxi TIAN and Suizheng QIU |Show fewer author(s)
Author Affiliations
  • Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China
  • show less
    References(23)

    [1] Ritchie I G. Waterside corrosion of zirconium alloys in nuclear power plants[R]. Technical Report IAEA TECDOC 996(1998).

    [2] Gilmore P M, Klepfer H H, Sorensen J M. EPRI PWR fuel cladding corrosion (PFCC) model Volume 1: theory and users manual[R]. Technical Report TR-105387-V1(1995).

    [8] CUI Yiran, YANG Zhongbo. Effect of hydrogen on mechanical properties of zirconium alloy for nuclear use[J]. Materials Reports, 36, 266-270(2022).

    [22] Merlino J. Experiments in hydrogen distribution in thermal gradients calculated using bison[D](2019).

    [24] Zhang J H. Hydruration du Zircaloy-4 et Etude de la distribution de l'Hydrogène dans une Gaine de Combustible REP[D](1993).

    Tools

    Get Citation

    Copy Citation Text

    Nan CHEN, Fengrui XIANG, Yanan HE, Yingwei WU, Jing ZHANG, Guanghui SU, Wenxi TIAN, Suizheng QIU. Development and validation of models for fuel rod oxidation and hydrogen pick-up behaviors in pressurized water reactor[J]. NUCLEAR TECHNIQUES, 2024, 47(9): 090601

    Download Citation

    EndNote(RIS)BibTexPlain Text
    Save article for my favorites
    Paper Information

    Category: NUCLEAR ENERGY SCIENCE AND ENGINEERING

    Received: Jan. 16, 2024

    Accepted: --

    Published Online: Nov. 13, 2024

    The Author Email:

    DOI:10.11889/j.0253-3219.2024.hjs.47.090601

    Topics