Comparative analysis of the long-term strength of Russian ferritic-martensitic reactor steels

IF 3.3 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-02-01 Epub Date: 2024-12-18 DOI:10.1016/j.jnucmat.2024.155575

N.V. Kataeva , V.V. Sagaradze , V.A. Zavalishin , K.A. Kozlov , V.A. Sirosh , M.V. Leont'eva-Smirnova , A.A. Nikitina

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Abstract

The paper presents the results of long-term high-temperature creep tests of Russian reactor steels with ferritic-martensitic structure (the duration of some measurements exceeded 8 years). In the current study, the structural-phase transformations, characteristics of creep and long-term strength at 650 °C, 670 °C, and 700 °C under 60–140 MPa in oxide-free and oxide containing steels were determined. The creep tests were performed on specially designed transverse micro-specimens prepared from fuel elements cladding used in the fast-neutron reactor. The creep velocity of the ferritic-martensitic reactor steels was established to be specified by resistance of lath martensite and ferrite structures to diffusion processes of return and recrystallization. The most heat-resistant oxide-free steel contains the largest amount of refractory elements and carbides. The best heat resistance was observed for the steel hardened with thermal-resistant yttrium-titanium nanooxides. The samples made of this steel demonstrated one order less creep velocity at 700 °C under 100 MPa and 100-fold time to fracture in comparison with the oxide-free reactor steels.

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俄罗斯铁素体-马氏体反应器钢长期强度的对比分析

本文介绍了俄罗斯铁素体-马氏体结构反应堆钢的长期高温蠕变试验结果（有些试验持续时间超过8年）。在本研究中，研究了无氧化物和含氧化物钢在60-140 MPa、650℃、670℃和700℃下的组织相转变、蠕变特性和长期强度。用快中子反应堆燃料元件包壳制备了专门设计的横向微试样，进行了蠕变试验。建立了铁素体-马氏体反应器钢的蠕变速度，用板条马氏体和铁素体组织对回流和再结晶扩散过程的阻力来表示。最耐热的无氧化物钢含有最多的耐火元素和碳化物。用耐高温钇钛纳米氧化物硬化的钢具有最佳的耐热性。与无氧反应器钢相比，用该钢制成的试样在700℃、100 MPa下的蠕变速度降低了一个数量级，断裂时间缩短了100倍。

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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.