• 熔盐堆用合金在多环境耦合（辐照/腐蚀/应力）下的服役性能评价与失效机制研究；
• 金属材料的离子辐照损伤表征与抗辐照材料开发；
• 镍基合金高温氦脆研究；

每年招收硕士、直博、硕博研究生各1名

招生专业

核能科学与工程，材料科学与工程，材料与化工；

招生方向

材料腐蚀、离子辐照、材料加工

2014-04--2017-06   上海交通大学   博士
2011-09--2014-03   上海交通大学   硕士

   

2026-01~现在, 中国科学院上海应用物理研究所, 研究员
2025-06~2025-12,中国科学院上海应用物理研究所, 副研究员
2020-03~2025-06,西北工业大学, 副教授
2018-01~2020-12,密歇根大学-安娜堡分校, 博士后/助理研究科学家
2017-07~2017-12,上海交通大学, 博士后

2026-05-04-今,Annual of nuclear energy 审稿人,
2025-06-03-今,Corrosion communication 审稿人,
2024-08-06-今,Scripta Materila 审稿人,
2024-06-01-2026-06-01,青年编委, 《材料保护》青年编委
2022-06-01-今,Journal of Materials Research and Technology 审稿人,
2018-01-04-今,Jounal of Nuclear Materials 审稿人,
2016-06-01-今,Corrosion Science 审稿人,

（ 1 ） 一种高温熔盐环境中辐照样品的四点弯应力腐蚀测试夹具及其测试方法, 发明专利, 2026, 第 1 作者, 专利号: 202610045738.2

   

（1） Silicon segregation enhances IASCC of austenitic stainless steels via oxide degradation: Decoupling from chromium depletion effects, Corrosion Science, 2026, 第 1 作者  通讯作者
（2） Hafnium-enabled radiation tolerance in additively manufactured 316L stainless steel, Journal of Materials Science & Technology, 2026, 第 1 作者
（3） Stress corrosion cracking of additively manufactured 316 L stainless steels with varying Si contents in high temperature water, Corrosion Science, 2026, 第 5 作者  通讯作者
（4） Anisotropic behavior of delayed hydride cracking in Zr-2.5 Nb pressure tube, Journal of Nuclear Materials, 2026, 第 3 作者
（5） Elucidating the role of Nb on the long-term uniform corrosion of FeCrAl alloy in a simulated PWR environment, Corrosion Science, 2025, 第 1 作者  通讯作者
（6） Unveiling the role of irradiation in stress corrosion cracking of alloy 690, Corrosion Science, 2025, 第 1 作者
（7） Effects of chromium concentration on the uniform corrosion behavior of FeCrAl alloy in hydrogenated water, Journal of Nuclear Materials, 2025, 第 4 作者  通讯作者
（8） Microstructure instability of additively manufactured alloy 718 fabricated by laser powder bed fusion during thermal exposure at 600–1000 ℃, Journal of Alloys and Compounds, 2025, 第 4 作者
（9） New insights into radiation damage in additively manufactured alloy 718, Additive Manufacturing, 2025, 第 3 作者
（10） Effect of aging at 400° C on microstructure and corrosion properties of Fe-13Cr-3.5 Al-2Mo-1.5 Nb alloy, Journal of Nuclear Materials, 2025, 第 8 作者
（11） Effect of Trace Hf on Microstructure and Mechanical Property of Additive Manufacturing 316L Stainless Steel, Atomic Energy Science and Technology, 2025, 第 4 作者  通讯作者
（12） Empowering oxidation resistance of Cr-coated zirconium alloys via hydrogen-driven interface polymorphic transformation, Acta Materialia, 2025, 第 6 作者
（13） Effects of Si on stress corrosion cracking properties of austenitic stainless steel, Rare Metal Materials and Engineering , 2025, 第 4 作者  通讯作者
（14） IASCC of 304 SS in BWR environments: Effects of post-irradiation annealing and surface condition, Corrosion Science, 2025, 第 1 作者  通讯作者
（15） Corrosion behavior of Nb-doped FeCrAl alloy in 500°C steam, Corrosion Science, 2024, 第 5 作者  通讯作者
（16） Hydrogen embrittlement of FeCrAl alloys: The significant role of Laves phase and AlN particles, Materials Science and Engineering: A, 2024, 第 2 作者  通讯作者
（17） Effect of hydride orientation on tensile properties and crack formation in zirconium alloy cladding tubes, Journal of Nuclear Materials, 2024, 第 4 作者
（18） A comparison study of high purity nickel fabricated by laser powder bed fusion and subjected to dynamic plastic deformation, Materialia, 2024, 第 4 作者
（19） A high-resolution characterization of irradiation-assisted stress corrosion cracking of proton-irradiated 316L stainless steel in simulated pressurized water reactor primary water, Corrosion Science, 2022, 第 3 作者
（20） IASCC of neutron irradiated 316 stainless steel to 125 dpa, Materials characterization, 2021, 第 1 作者
（21） Crack initiation of neutron-irradiated 304 L stainless steel in PWR primary water, Corrosion Science, 2021, 第 1 作者  通讯作者
（22） Environment assisted cracking of 308L weld metal in high temperature water, Journal of Nuclear Materials, 2021, 第 7 作者
（23） A comparison study of void swelling in additively manufactured and cold-worked 316L stainless steels under ion irradiation, Journal of Nuclear Materials, 2021, 第 5 作者
（24） Effect of dissolved oxygen and hydrogen on the stress corrosion cracking behavior of alloy 600 in high temperature water, Journal of Nuclear Materials, 2021, 第 4 作者
（25） Microstructural investigation of the nodular corrosion of 304NG stainless steel in supercritical water, Corrosion Science, 2020, 第 1 作者
（26） Effect of deformation level and orientation on SCC of 316L stainless steel in simulated light water environments, Journal of Nuclear Materials, 2020, 第 1 作者  通讯作者
（27） Corrosion fatigue crack growth behavior of alloy 52 M in high-temperature water, Journal of Nuclear Materials, 2020, 第 4 作者
（28） Effect of intergranular carbides on the cracking behavior of cold worked alloy 690 in subcritical and supercritical water, Corrosion Science, 2020, 第 4 作者
（29） Stress corrosion cracking of the fusion boundary for 304l/82 dissimilar metal weld joint in simulated primary water, CORROSION, 2020, 第 4 作者
（30） Environmentally assisted cracking of forged 316LN stainless steel and its weld in high temperature water, Corrosion Science, 2019, 第 1 作者
（31） Grain boundary engineering of large-size 316 stainless steel via warm-rolling for improving resistance to intergranular attack, Materials Letters, 2019, 第 3 作者
（32） Observation of internal oxidation in a 20% cold-worked Fe-17Cr-12Ni stainless steel through high-resolution characterization, Scripta Materialia, 2019, 第 5 作者
（33） Effect of δ-ferrite on the stress corrosion cracking behavior of 321 stainless steel, Corrosion Science, 2019, 第 4 作者
（34） An insight into PWR primary water SCC mechanisms by comparing surface and crack oxidation, Corrosion Science, 2019, 第 2 作者
（35） Comparison of the stress corrosion cracking growth behavior of cold worked Alloy 690 in subcritical and supercritical water, Journal of Nuclear Materials, 2019, 第 4 作者
（36） Effects of chloride and oxygen on stress corrosion cracking of cold worked 316/316L austenitic stainless steel in high temperature water, Corrosion Science, 2016, 第 1 作者
（37） SCC crack growth rate of cold worked 316L stainless steel in PWR environment, Journal of Nuclear Materials, 2015, 第 1 作者

   

（ 1 ） 熔盐堆用先进材料离子辐照筛选研究 , 负责人, 研究所自主部署, 2026-06--2028-12
（ 2 ） 钍基熔盐堆用高性能结构材料研发, 负责人, 境内委托项目, 2026-01--2027-12
（ 3 ） 纳米ZrC弥散增强FeCrAl合金的辐照损伤与腐蚀机理研究, 负责人, 国家任务, 2024-01--2027-12
（ 4 ） 临氢关键材料服役性能评价技术研究, 参与, 国家任务, 2023-12--2027-11
（ 5 ） 增材制造316L不锈钢组织调控与抗辐照损伤性能的高通量研发, 负责人, 地方任务, 2022-10--2024-09
（ 6 ） 铪对增材制造316L不锈钢组织演变和辐照损伤影响的研究, 负责人, 地方任务, 2022-08--2023-07
（ 7 ） 核级690合金辐照加速应力腐蚀开裂机理研究, 负责人, 国家任务, 2022-01--2024-12
（ 8 ） 汽车用6系高性能挤压铝合金型材开发, 负责人, 境内委托项目, 2021-08--2025-08
（ 9 ） 局部变形对一回路中不锈钢晶界氧化及裂纹萌生的影响, 负责人, 国家任务, 2018-11--2019-10
（ 10 ） 主管道异种金属焊接接头工艺性能评价, 负责人, 境内委托项目, 2017-12--2018-12
（ 11 ） 核电关键材料服役行为的高通量评价与预测技术, 参与, 国家任务, 2017-07--2021-06

（1）镍基690合金的辐照加速应力腐蚀开裂   2025年辐照效应分会年会   2026-06-08
（2）Nb添加对FeCrAl合金长期腐蚀性能的影响   2025年度第四届ATF燃料技术会议   2025-11-07
（3）Elucidating the effects of Si segregation on IASCC   2024-10-05
（4）Hf对增材制造316不锈钢氦致损伤的影响   中国核学会辐照效应分会2024年度学术年会   2024-08-21
（5）退火热处理对中子辐照304不锈钢应力腐蚀开裂缓解的研究   第三界中国新材料产业大会   2021-10-21
（6）中子辐照 304、316 不锈钢在压水堆环境中的应力腐蚀开裂   中国核学会 2021 年学术年会   2021-10-19
（7）IASCC of neutron irradiated 316 in simulated PWR primary water   2019-08-18