METALS AND METAL MATRIX COMPOSITES |
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Effects of Ratios of Strong Carbide-forming Elements to C and Stabilization Treatment on Precipitation Behavior of 310S Austenitic Stainless Steel |
WEN Donghui1, LYU Yang1, LI Zhen2, WANG Qing1, TANG Rui3, DONG Chuang1
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1 Key laboratory of Materials Modification by Laser, Ion and Electron Beams (Ministry of Education), School of Materials Science and Engineering, Dalian University of Technology, Dalian 116024 2 School of Mechanical Engineering, Dalian University of Technology, Dalian 116024 3 Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu 610213 |
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Abstract High Cr/Ni 310S-type austenitic stainless steels (ASSs) exhibit good comprehensive properties of creep-, corrosion- and oxidation-resis-tances, as well as moderate neutron irradiation-resistance, which are potential as fuel-cladding candidate materials applied into the super-critical water reactors (SCWRs). However, one underlying issue for this kind of ASSs is their microstructural stability, i.e., a large amount of coarse Cr23C6 and σ are precipitated on grain boundaries (GBs) after a long-term aging at 873—1 123 K, as a result of the embrittlement and intergranular corrosion of materials. In order to improve their microstructural stability at high temperatures, the present work investigated systematically the effects of the ratios of strong carbide-forming elements M (M=Nb, Ti, Ta, and Zr) to C (in atomic percent at%), and the stabilization treatment on the precipitation behaviors of 310S ASS. The designed alloy rods were solid-solutioned at 1 473 K for 0.5 h plus water quenched, stabilized at 1 173 K for 0.5 h, and then aged at 1 073 K for 24 h. The microstructure and precipitated phases at different heat-treatment states were characterized with OM, SEM-EDS, EPMA and TEM, respectively. It was found that the addition of M favors to the precipitation of MC-type carbides effectively. A high ratio of M to C (2/1) can accelerate the formation of brittle σ phase, in contrast, only Cr23C6 precipitates exist on GBs after 1 073 K/24 h aging in alloys with M/C=1/1. In addition, the Cr23C6 could be inhibited effectively by stabilization heat-treatment. This work provides effective basic data support for the development of fuel cladding materials for SCWRs, and point the way for the further research.
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Published: 31 July 2019
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Fund:This work was financially supported by the International Science & Technology Cooperation Program of China (2015DFR60370), the National Key Research and Development Plans (2017YFB0702400) and the National Magnetic Confinement Fusion Energy Research Project (2015GB121004). |
About author:: Donghui Wenreceived his Bachelor degree of engineering in July 2014 from Dalian Jiaotong University. He is currently a successive postgraduate and doctoral student in School of Materials Science and Engineering, Dalian University of Technology, focus on the composition optimization and microstructural stability of stainless steels for nuclear fuel cladding materials. Qing Wangreceived her Ph.D.degree in November 2005 from Dalian University of Technology. She is currently a Professor and Ph.D. supervisor in School of Materials Science and Engineering, Dalian University of Technology. Her research interest are materials composition design and development of multi-component alloys, including the stainless steels, Ti-alloys, high-entropy alloys and superalloys. |
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