NUCLEAR TECHNIQUES, Volume. 46, Issue 7, 070602(2023)

Research on corrosion release model for nuclear metallic materials based on PBR

Changying LI, Desheng JIN, and Yulong MAO*
Author Affiliations
  • China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen 518000, China
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    References(21)

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    [5] Maeng W Y, Choi B S, Min D K et al. The status of AOA in Korean PWR and a study on the CRUD deposition on cladding surface[C](2009).

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    [10] Doncel N, Chen J, Gillén P et al. On the role of nickel deposition in a CIPS occurrence in PWR[C](2008).

    [14] Deshon J. Modeling PWR fuel corrosion product deposition and growth process[R](2005).

    [16] Zhengyin HAI, XIN Changsheng, WANG Hui. Corrosion behavior of nuclear structural materials in Zn-added coolant[J]. Rare Metal Materials and Engineering, 48, 683-687(2019).

    [17] JIANG Suqing. The effects of zinc injection on corrosion behaviors of PWR primary loop structural materials[D](2011).

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    Changying LI, Desheng JIN, Yulong MAO. Research on corrosion release model for nuclear metallic materials based on PBR[J]. NUCLEAR TECHNIQUES, 2023, 46(7): 070602

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    Paper Information

    Category: Research Articles

    Received: Sep. 18, 2022

    Accepted: --

    Published Online: Aug. 3, 2023

    The Author Email:

    DOI:10.11889/j.0253-3219.2023.hjs.46.070602

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