Under the microscope: Reduced activation ferritic martensitic steel Eurofer-97 following ion-Irradiation and high-temperature high-pressure water exposure

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Ronald N. Clark , David Kumar , Jonathan Hawes , Liam Hughes , Mariia Zimina , Robert Burrows , Jean-Charles Eloi , James Hargreaves , Kun Mo , Dong Liu , Elizabeth H. ParkerQuaife , Tomas Martin
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Abstract

This study is designed to characterise the microstructural behaviour of Eurofer-97 steel under ion irradiation and subsequent exposure to high-temperature high-pressure (HTHP) water. Eurofer-97, a ferritic-martensitic steel, has been developed to withstand the conditions of fusion reactors in the locations in contact with coolant with an elevated level of neutron flux, such as the breeder-wall blanket. The material has been studied after self-ion irradiation (using Fe ions) simulating the microstructural effects of neutron irradiation limited to the subsurface layer. The corrosion properties of the Eurofer-97 steel were studied by exposure to HTHP water up to 331°C. Advanced microstructural characterisation using scanning, transmission electron and focused ion beam microscopy was performed on the as-received microstructure and after ion irradiation. This was then characterised after exposure for 240 h in high-temperature water. Eurofer-97 had a dense, columnar Cr-rich inner oxide, followed by a Fe-rich outer oxide layer. In the irradiated condition the grain structure and oxide itself was less ordered. No appreciable difference in oxide thickness was identified between the irradiated and unirradiated specimens after this short exposure time.
显微镜下:离子辐照和高温高压水暴露后活化度降低的铁素体马氏体钢 Eurofer-97
本研究旨在描述 Eurofer-97 钢在离子辐照和随后暴露于高温高压 (HTHP) 水下的微观结构特性。Eurofer-97 是一种铁素体-马氏体钢,开发用于承受聚变反应堆中与中子通量水平较高的冷却剂接触位置(如增殖体壁毯)的条件。对这种材料进行了自离子辐照(使用铁离子)后的研究,模拟了仅限于次表层的中子辐照的微观结构影响。通过暴露在温度高达 331°C 的 HTHP 水中,对 Eurofer-97 钢的腐蚀特性进行了研究。使用扫描电子显微镜、透射电子显微镜和聚焦离子束显微镜对收到的微观结构和离子辐照后的微观结构进行了先进的微观结构表征。然后在高温水中辐照 240 小时后进行表征。Eurofer-97具有致密的柱状富铬内氧化层,其次是富铁外氧化层。在辐照条件下,晶粒结构和氧化物本身的有序性较差。在短时间的辐照后,辐照试样和未辐照试样的氧化物厚度没有明显差异。
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来源期刊
Journal of Nuclear Materials
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.
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