Development of irradiation- and high-temperature resistant steels for fusion applications: Belgian contribution

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-02-01 DOI:10.1016/j.jnucmat.2025.155611
D. Terentyev , O. Kachko , A. Puype , S. Valiyev , K. Iroc , A. Zinovev
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Abstract

In this work, we investigate alternative routes for the production of reduced activation ferritic-martensitic (RAFM) steels aiming to achieve specific improvements of their performance under fusion operational conditions. The latter impose at least two specific challenges: (i) low-temperature embrittlement (LTE) and (ii) high-temperature creep (HTC) deformation. In this work, we review the optimization routes attempted to alleviate the above noted challenges which are otherwise met in EUROFER97 steel. The development routes include: (i) reduction of manganese and carbon content coupled with alternation of other chemical elements and followed by quench & rolling procedures; (ii) alternation of spatial distribution and structural morphology of carbonitrides by varying carbon, vanadium and tantalum content based on thermodynamic computations and followed by thermo-mechanical treatment optimization; (iii) doping with zirconium/titanium and increase of tantalum content to improve ductility and toughness. The targeted enhanced performance is achieved without compromising strength and DBTT. The results of the baseline characterization including mechanical tests and microstructural characterization are presented. The contribution of the microstructural features constituting the ferritic martensitic steels into the tensile strength is analyzed based on existing mechanistic models and discussed to rationalize the improvements achieved.

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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.
期刊最新文献
Editorial Board Effects of long-term thermal aging on mechanical properties and microstructural evolution of 17–4 PH stainless steel in simulated thermal conditions for nuclear applications Dispersed barrier hardening modeling on depth-distributed helium bubbles in iron-based alloys Microstructural stability and mechanical property of novel high-Si high-Cr reduced activation ferritic/martensitic steels at high temperatures Development of irradiation- and high-temperature resistant steels for fusion applications: Belgian contribution
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