导师队伍

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陈胜虎

  • 电话: 024-23971981
  • 邮箱: chensh@imr.ac.cn
  • 所属部门: 特种合金研究部

研究方向

先进核能系统用高性能结构材料研发:
高强度耐液态金属腐蚀奥氏体不锈钢的设计与组织性能调控
先进核能系统用奥氏体不锈钢的服役行为与评价方法
先进核能系统用高性能铁素体/马氏体钢的设计与制备

代表论著

围绕核能系统用高性能奥氏体不锈钢、铁素体/马氏体钢的研发与制备技术,发表论文30余篇,申请发明专利20余项。近期发表学术论文:
[1] Qiyu Wang, Shenghu Chen*, Xinliang Lv, Haichang Jiang, Lijian Rong*, The role of δ-ferrite in fatigue crack growth of AISI 316 austenitic stainless steel, Journal of Materials Science & Technology (Accepted).
[2] 陈胜虎*,戎利建,超细晶铁素体-马氏体钢的高温氧化成膜特性及其对Pb-Bi腐蚀行为的影响,金属学报,57 (2021) 989-999.
[3] Shenghu Chen*, Xiaojie Jin, Lijian Rong, Microstructural evolution and mechanical properties of ultrafine-grained ferritic-martensitic steel during thermal aging, Metallurgical and Materials Transactions A, 51(2020) 5154-5168.
[4] Qiyu Wang, Shenghu Chen*, Lijian Rong*, δ-Ferrite formation and its effect on the mechanical Properties of heavy-section AISI 316 stainless steel casting, Metallurgical and Materials Transactions A, 51 (2020) 2998-3008.
[5] Shenghu Chen*, Honglei, Hu, Mingjiu Zhao, Lijian Rong, Effect of post-weld aging treatment on the precipitation and mechanical behavior of Fe-Ni based alloy weldment, Materials Science & Engineering A, 718 (2018) 363-370.
[6] Xiaojie Jin, Shenghu Chen*, Lijian Rong*,Effect of Fe2Zr phase on the mechanical properties and fracture behavior of Fe-Cr-W-Zr ferritic alloy, Materials Science & Engineering A, 722 (2018) 173-181.
[7] Xiaojie Jin, Shenghu Chen*, Lijian Rong*,Microstructure modification and mechanical property improvement of reduced activation ferritic/martensitic steel by severe plastic deformation,Materials Science & Engineering A, 712 (2018) 97-107.
[8] Shenghu Chen*, Lijian Rong*, Roles of Mn in the high-temperature air oxidation of 9Cr ferritic–martensitic steel after severe plastic deformation, Oxidation of Metals, 89 (2018) 415-428.
[9] 陈胜虎*,戎利建,Ni-Fe-Cr合金固溶处理后的组织变化及其对性能的影响,金属学报,54 (2018) 385-392.
Xiaojie Jin, Shenghu Chen*, Lijian Rong*, Effects of Mn on the mechanical properties and high temperature oxidation of 9Cr2WVTa steel, Journal of Nuclear Materials, 494 (2017) 103-113.