Nitriding model for zirconium based fuel cladding in severe accident codes

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

Journal of Nuclear Materials Pub Date : 2023-08-15 DOI:10.1016/j.jnucmat.2023.154466

B.S. Jäckel , J.C. Birchley , T. Lind , M. Steinbrück , S. Park

引用次数: 0

Abstract

A model has been developed to describe the nitriding of partially oxidized zirconium based cladding during an air ingress sequence when the reaction has become starved of oxidant (oxygen and/or steam), and the subsequent re-oxidation of nitride following of restoration of coolant. Key aspects of the model are the estimation of oxygen-stabilised alpha zirconium, α-Zr(O), formed during pre-oxidation and its reaction with the nitrogen. Nitriding of metallic Zr is much slower than α-Zr(O), and plays a comparatively minor role. The model is based on data from separate-effects tests comprised pre-oxidation, nitriding in the absence of oxidant, and re-oxidation in the absence of nitrogen, which were used to derive the kinetic parameters for the main reaction processes. Developmental assessment was performed using the test results, demonstrating favourable agreement for the main reaction signatures. Independent assessment against Integral Test data is underway.

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重大事故规范中锆基燃料包壳的氮化模型

已经建立了一个模型来描述部分氧化锆基包层在反应中缺乏氧化剂(氧气和/或蒸汽)时在空气进入序列中的氮化，以及在冷却剂恢复后氮化的再氧化。该模型的关键方面是预氧化及其与氮反应过程中形成的氧稳定α锆α-Zr(O)的估计。金属Zr的氮化比α-Zr(O)慢得多，作用相对较小。该模型基于预氧化、无氧化剂渗氮和无氮再氧化的分离效应试验数据，并利用这些数据推导出主要反应过程的动力学参数。利用测试结果进行了发展评估，证明了主要反应特征的良好一致性。针对积分测试数据的独立评估正在进行中。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.