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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    Background

    The metallic materials utilized for nuclear reactors undergo corosion due to the inherient high-temperature and high-pressure environment. Consequently, the corrosion products may be deposited in the core, called crud, and impact the fuel operation, core reactivity, and primary radioactivity, such as crud-induced localized corrosion or crud-induced power shift.

    Purpose

    Thus, this study aimed to establish a model that can quantitatively analyze these corrosion products, the results of which can then be used to evaluate the impact of these products.

    Methods

    Based on the corrosion and release dynamic theory, combined with the assumption of metallic oxide volume ratio (Pilling-Bedworth Ratio), a corrosion and release model of metallic materials was developed. The model was validated based on experimental data from Inconel 690.

    Results

    The verification result indicates that the proposed model is reasonable and scientific, and hence can be used to quantify the amount of main corrosion and release products of metallic materials for nuclear reactors.

    Conclusions

    This study provides a model of the main elements of corrosion products including Ni and Fe ferrite for PWR plants, which can be used for evaluating the impact of corrosion products. However, some of the microelements of corrosion cannot be quantified by using this model as the corresponding equations were over-determined. Hence this aspect requires further research in the future.

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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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