NUCLEAR TECHNIQUES, Volume. 48, Issue 4, 040602(2025)

Prediction model of fouling radioactive distribution in primary loop of pressurized water reactor

Shiwei WANG1,2, Xiaojing LIU1,2, Tengfei ZHANG1,2, and Hui HE1,2、*
Author Affiliations
  • 1School of Mechanical Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
  • 2Shanghai Digital Nuclear Reactor Technology Intergration Innovation Center, Shanghai 200240, China
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    [12] Kang S, Sejvar J. CORA-II model of PWR corrosion-product transport[R]. EPRI NP-4246(1985).

    [20] Best S E. Characterization of the MIT research reactor for fusion reactor related studies[D]. Department of Nuclear Engineering(1979).

    [22] Wicks J H. Design, construction and testing of an in-pile loop for PWR simulation[D](1987).

    [23] Bergmann C A, Durkosh D E, Lindsay W T et al[M]. The role of coolant chemistry in PWR radiation-field buildup, 2-18(1985).

    [24] LIU Xinfu. Influence of primary water chemistry of PWR on the integrity of fuel cladding[D](2007).

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    Shiwei WANG, Xiaojing LIU, Tengfei ZHANG, Hui HE. Prediction model of fouling radioactive distribution in primary loop of pressurized water reactor[J]. NUCLEAR TECHNIQUES, 2025, 48(4): 040602

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    Paper Information

    Category: NUCLEAR ENERGY SCIENCE AND ENGINEERING

    Received: Dec. 19, 2023

    Accepted: --

    Published Online: Jun. 3, 2025

    The Author Email: Hui HE (何辉)

    DOI:10.11889/j.0253-3219.2025.hjs.48.230476

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