基于氧化模型的压水堆包层表面沉积物腐蚀风险预测

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2023-08-26 DOI:10.1016/j.jnucmat.2023.154698

Yuan Shen , Shiyu Tan , Yunchen Lai , Hongguo Hou , Nan Chao , Caishan Jiao , Yu Zhou , Yang Gao

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引用次数: 0

摘要

堆积物(CRUD)引起的熔覆层表面温度和物质浓度的升高，增加了压水堆熔覆层腐蚀的风险。本文建立了一个氧化模型，可以准确预测在较宽的硼和锂浓度范围内压水堆中Zr-4包层的腐蚀。将该氧化模型与局部热-水力模型相结合，对不同工况、水化学条件和CRUD结构参数下的CRUD局部腐蚀(CILC)进行了预测和分析。腐蚀风险值清楚地反映了不同条件对CILC的影响。

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Development of an oxidation model for the prediction of the corrosion risk induced by deposits on cladding surface in PWRs

The enhancement of the temperature and the concentration of the species on the cladding surface induced by deposits (CRUD) increases the risk of the cladding corrosion in PWR. An oxidation model is developed to accurately predict the corrosion of the Zr-4 cladding in PWRs under the wide range of the boron and lithium concentrations here. Combining this oxidation model with the local thermal-hydraulic model, the CRUD induced local corrosion (CILC) is well predicted and analyzed under various operational conditions, hydrochemical conditions, and CRUD structural parameters. The effects of different conditions on CILC are clearly reflected by the corrosion risk values.

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来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.