2011.10-2014.09，Tohoku University（日本东北大学），核能科学与工程，博士
2008.09-2011.07，郑州大学，材料加工工程，硕士
2004.09-2008.06，郑州大学，材料科学与工程，学士

2022.09-至今，bat365官方网站，核科学与工程学院，长聘教轨副教授
2017.11-2022.08，东京大学，核能系（重照射研究设施部门），助理教授
2016.04-2017.10，东京大学，核能系，助理研究员
2014.10-2016.03，日本东北大学，金属材料研究所（核工程材料研究部门），博士后

核材料安全行为研究：
1. 先进材料辐照效应研究
2. 高安全核材料研发
3. 事故下堆内材料行为研究

欢迎对核材料相关研究感兴趣的本科、硕士、博士、博士后联系

2022-2026 日本学术振兴会，科研费基盘研究B：基体-析出相界面的吸氢效应与辐照效应的协同作用机理研究（子课题负责人）
2020-2024 日本文部科学省，国家课题对应型研究开发项目：金属涂层锆合金事故容错型核燃料包壳材料的研发（子课题负责人）
2020-2023 日本文部科学省，英知-福岛事故反应堆退役项目：福岛事故核燃料碎片研究（主持）
2019-2022 日本学术振兴会，科研费若手研究：核工程结构材料的辐照硬化与结晶取向的关联性研究（主持）
2018-2022 日本学术振兴会，科研费基盘研究B：吸氢对核材料的辐照行为的促进／抑制效果研究（子课题负责人）

【2023年度】
[1] Z.H. Hong*, M. Pellegrini, N. Erkan, H.Y. Liao, H.L. Yang, H. Yamano, K. Okamoto, A quantitative method of eutectic reaction study between boron carbide and stainless steel, Annals of Nuclear Energy, 180 (2023) 109462.

【2022年度】
[1] S. Kano*, H.L. Yang*, K. Murakami, H. Abe, Modification of the high fluence irradiation facility at the University of Tokyo: Assessment of radiation-induced amorphization of Zr(Cr,Fe)2 Laves phase under 180 keV-He+ irradiation, Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 531 (2022) 1-8.
[2] L.J. Cui, H.L. Yang*, Y.F. Du, Q.Q. Shi, S. Kano, H. Abe*, TEM characterization of irradiation-induced dislocation loops and voids in ion-irradiated pure chromium, Journal of Nuclear Materials, 569 (2022)153920.
[3] B. Li, H.L. Yang*, R. Holmes, Z.Q. Wei, S. Kano, H. Abe*, Microstructure evolution and mechanical property of high temperature solid-state diffusion bonded Cr-Zry4 with and without a 316 SS interlayer, Nuclear Materials and Energy, 32(2022) 101233.
[4] H.L. Yang*, Anisotropic effects of radiation-induced hardening in nuclear structural materials: A review, Journal of Nuclear Materials, 561 (2022) 153571.
[5] S. Kano*, H.L. Yang, J. McGrady, M. Nakajima, M. Ando, T. Nozawa, H. Abe, Phase decomposition of oxide film of flow accelerated corroded F82H steel under high-temperature iron irradiation, Journal of Nuclear Materials, 563 (2022) 153639.
[6] S. Kano*, H.L. Yang, J. McGrady, Y. Watanabe, M. Ando, D. Hamaguchi, T. Nozawa, H. Tanigawa, K. Yoshida, T. Shibayama, H. Abe, Radiaion-induced amorphization of M23C6 in F82H steel: An atomic-scale observation. Journal of Nuclear Materials, 558 (2022) 153345.
[7] D. Chen*, K. Murakami, H.L. Yang, L. Chen, H. Abe, Z. Li, H. Sekimura. Flux effects on point defect behavior by tracking loop evolution using combined irradiation method, Scritpa Materialia, 207 (2022) 114311.

【2021年度】
[1] H.L. Yang*, S. Kano, J. McGrady, J.J. Shen, Y.F. Li, D.Y. Chen, K. Murakami, H. Abe. Hardening behavior and deformation microstructure beneath indentation in heavy ion irradiated 12Cr-ODS steel at elevated temperature, Journal of Nuclear Materials, 543 (2021) 152606.
[2] Vu Nhut Luu*, K. Murakami*, H. Samouh, I. Maruyama, T. Ohkubo, P. Tom, L. Chen, S. Kano, H.L. Yang, H. Abe, K. Suzuki, M. Suzuki. Changes in properties of alpha-quartz and feldspars under 3 MeV Si-ion irradiation, Journal of Nuclear Materials, 545 (2021) 152734.
[3] J. McGrady*, S. Yamashita, S. Kano, H.L. Yang, H. Abe. Change transfer across the Cr2O3, Fe2O3, and ZrO2 oxide/water interface: A pulse radiolysis study, Radiation Physics and Chemistry, 180 (2021) 109240.
[4] J. McGrady*, S. Yamashita, S. Kano, H.L. Yang, A. Kimura, A. Abe. H2 generation at metal oxide particle surfaces under γ-radiation in water, Journal of Nuclear Science and Technology, 2021, 58, 604-609.
[5] H.L. Yang, K. Murakami. Investigation of environment induced property change and cracking behavior in fuel debris, Japan Atomic Energy Agency (JAEA)-Review 2021, 84 pages, 2021-058. DOI:10.11484/jaea-review-2021-058（In Japanese）

【2020年度】
[1] H.L. Yang*, S. Kano, J. McGrady, D.Y. Chen, K. Murakami, H. Abe. Microstructural evolution and hardening effect in low-dose self-ion irradiated Zr-Nb alloys, Journal of Nuclear Materials, 542 (2020) 152523.
[2] H.L. Yang*, S. Kano, J.J. Shen, J. McGrady, Y.F. Li, D.Y. Chen, K. Murakami, H. Abe. Investigation of anisotropic hardening response in a 12Cr-ODS ferritic steel subjected to 2.8 MeV Fe2+ irradiation, Journal of Nuclear Materials, 531 (2020) 152016.
[3] S. Kano*, H.L. Yang, J. McGrady, D. Hamaguchi, M. Ando, H. Tanigawa, H. Abe.Study of radiation-induced amorphization of M23C6 in RAFM steels under iron irradiations. Journal of Nuclear Materials, 533 (2020) 152088.
[4] J.J. Shen*, T. Nadasaka, T. Muroga, H.L. Yang, S. Kano, H. Abe. Microstructural evolution of two-way cold rolled 12Cr ODS steel under 1073-1373 K annealing, Nuclear Materials and Energy, 25 (2020) 100792.
[5] V. N. Luu*, K. Murakami*, H. Samouh, I. Maruyama, K. Suzuki, P. P. Tom, L. Chen, S. Kano, H.L. Yang, H. Abe, M. Suzuki. Swelling of alpha-quartz induced by MeV ions irradiation: Critical dose and swelling mechanism, Journal of Nuclear Materials, 539 (2020) 152266.
[6] S. R. Oh, S. Kano, H.L. Yang, J. McGrady, H. Abe*. Radiation-induced nanoparticle growth in 12Cr ODS steel at elevated temperature, Journal of Nuclear Materials, 538 (2020) 152195.
[7] J. McGrady*, S. Yamashita, A. Kimura, S. Kano, H.L. Yang, Z.G. Duan, T. Saito, H. Abe. γ-radiation effects on metal oxide particles and their wetted surfaces, Journal of Nuclear Science and Technology, 57 (2020) 463-471.
[8] Z.G. Duan, G.S. Xin, Y. Zhou, Y.M. Li, H. Abe, H.L. Yang, S. Kano, J. McGrady. Development of self-healing coating on fuel cladding for water-cooling nuclear reactors. GLOBAL 2019-International Nuclear Fuel Cycle Conference and TOP FUEL 2019 - Light Water Reactor Fuel Performance Conference 2020, Pages 1157-1163.

【2019年度】
[1] H.L. Yang*, S. Kano, L.J. Chai, J.J. Shen, Z.S. Zhao, J. McGrady, Z.G. Duan, D.Y. Chen, H. Abe. Interaction between slip and {10-12} tensile twinning in Zr alloy: Quasi in situ electron backscatter diffraction study under uniaxial tensile test, Journal of Alloys and Compounds, 782 (2019) 659-666.
[2] H.L. Yang*, S. Kano, J. McGrady, J.J. Shen, Y. Matsukawa, D.Y. Chen, K. Murakami, H. Abe*. Surface orientation dependence of irradiation-induced hardening in a polycrystalline zirconium alloy, Scripta Materialia, 162 (2019) 209-213.
[3] Z.G Duan*, H.L. Yang, S. Kano, J. McGrady, S. Gao, Y Zhou, H. Abe. Investigation on the feasibility of the interaction between NiO and Mo oxide for self-healing intelligence on the nuclear fuel cladding, Journal of Nuclear Science and Technology, 56 (2019) 1103-1109.
[4] J. Shen*, H.L. Yang, Y.F. Li, S. Kano, Y. Matsukawa, Y. Satoh, H. Abe. Recrystallization behavior of a two-way cold rolled 12Cr ODS steel, Fusion Engineering and Design, 143 (2019) 99-105.
[5] S. Kano*, H.L. Yang, J. McGrady, T. Ihara, T. Hazuku, H. Abe. Investigation of radiation-induced surface activation effect in austenitic stainless steel under ultraviolet and γ-ray radiations, Journal of Nuclear Science and Technology, 56 (2019) 300-309.
[6] S. Kano*, H.L. Yang, J. McGrady, T. Ihara, T. Hazuku, H. Abe. Wettability recovery behavior governed by desorption of hydroxyl species in steel, Langmuir, 35 (2019) 6830-6837.
[7] A. Meli*, H.L. Yang, J.J. Shen, S. Kano, H. Abe. High temperature tensile test of 12Cr ferritic ODS steel, International Journal of Ecosystems and Ecology Science, 9 (2019) 275-288.
[8] H. Abe*, S. Kano, H.L. Yang, S.R. Oh, H. Yasuda, T. Shibayama. In-situ Observations of instability of strengthening factors in steels under irradiations. Microscopy, 54 (2019) 122-125. (in Japanese).
[9] S.R. Oh, S. Kano, H.L. Yang, J. McGrady, H. Yasuda, H. Abe*. In-situ HVEM observation under 2 MeV electron irradiations on Y–Ti–O nanoparticles in 12Cr-ODS steel at 723K, Journal of Nuclear Materials, 524 (2019) 278-285.
[10] Y.F. Li*, J. Zhang, Y.Y. Shan, W. Yan, Q. Shi, K. Yang, J. Shen, T. Nagasaka, T. Muroga, H.L. Yang, S. Kano, H. Abe. Anisotropy in creep properties and its microstructural origins of 12Cr oxide dispersion strengthened ferrite steels. Journal of Nuclear Materials, 517 (2019) 307-314.
[11] J. Shen*, T. Nagasaka, T. Muroga, Y.F. Li, H.L. Yang, S. Kano, H. Abe. Study on anisotropy in microstructure and tensile properties of the 12Cr oxide dispersion strengthened (ODS) steel. Fusion Engineering and Design, 146 (2019) 1082-1085.
[12] S. Kano*, H.L. Yang, J. McGrady, T. Higuchi, Y. Etoh, H. Abe. Concurrent effects of irradiation and hydrogenation on microstructural and mechanical properties of Zr based fuel cladding alloys. 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, EnvDeg 2019, Pages 211-218.

【2018年度】
[1] H.L. Yang*, S. Kano, J.J. Shen, J. McGrady, Z.S. Zhao, Z.G. Duan, D.Y. Chen, H. Abe. On the strength-hardness relationships in a Zr-Nb alloy plate with bimodal basal texture microstructure, Materials Science and Engineering: A, 732 (2018) 333-340.
[2] Z.G. Duan, H.L. Yang, S. Kano, J. McGrady, H. Abe*. Application of chemical interaction between (Fe, Cr) oxides and Mo oxide at high temperature for self-healing intelligence on nuclear fuel cladding in LWRs, Journal of Nuclear Science and Technology, 55 (2018) 1402-1411.
[3] S. Kano*, H.L. Yang, J.J. Shen, Z.S. Zhao, J. McGrady, D. Hamaguchi, M. Ando, H. Tanigawa, H. Abe. Instability of MX and M23C6 type precipitates in F82H steels under 2.8 meV Fe2+ irradiation at 673 K, Nuclear Materials and Energy, 17 (2018) 56-61.
[4] J. Shen*, H.L. Yang, Z.S. Zhao, J. McGrady, S. Kano, H. Abe. Effects of pre-deformation on microstructural evolution of 12Cr ODS steel under 1473-1673K annealing. Nuclear Materials and Energy, 16 (2018) 137-144.
[5] S. Kano*, H.L. Yang, J.J. Shen, Z.S. Zhao, J. McGrady, D. Hamaguchi, M. Ando, H. Tanigawa, H. Abe. Investigation of instability of M23C6 particles in F82H steel under electron and ion irradiation conditions, Journal of Nuclear Materials, 502 (2018) 263-269.
[6] Z.G. Duan, H.L. Yang, S. Kano, K. Murakami, Y. Satoh, Y. Takeda, H. Abe*. Oxidation and electrochemical behaviors of Al2O3 and ZrO2 coatings on Zircaloy-2 cladding by thermal spraying, Surface and Coating Technology, 334 (2018) 319-327.

【2018年之前】
[1] H.L. Yang*, S. Kano*, Y. Matsukawa, J.J. Shen, Z.S. Zhao, Z.G. Duan, D.Y. Chen, K. Murakami, Y.F. Li, Y. Satoh, H. Abe. Tensile properties and microstructure of Zr-1.8Nb alloy subjected to 140-MeV C4+ ion irradiation, Journal of Nuclear Materials, 495 (2017) 138-145.
[2] Z.G. Duan*, H.L. Yang, Y. Satoh, K. Murakami, S. Kano, Z.S. Zhao, J.J. Shen, H. Abe*. Current status of materials development of nuclear fuel cladding tubes for light water reactors. Nuclear Engineering and Design, 316 (2017) 131-150.
[3] J.J. Shen*, H.L. Yang, Y.F. Li, S. Kano, Y. Matsukawa, Y. Satoh, H. Abe. Microstructural stability of an as-fabricated 12Cr-ODS steel under elevated-temperature annealing. Journal of Alloys and Compounds, 695 (2017) 1946-1955.
[4] Z.S. Zhao*, D. Kunii, T. Abe, H.L. Yang, J.J. Shen, Y. Shinohara, S. Kano, Y. Matsukawa, Y. Satoh, H. Abe. A comparative study of hydride-induced embrittlement of Zircaloy-4 fuel cladding tubes in the longitudinal and hoop directions. Journal of Nuclear Science and Technology, 54 (2017) 490-499.
[5] Y. Matsukawa*, S. Kitayama, K. Murakami, Y. Shinohara, K. Yoshida, H. Maeno, H.L. Yang, T. Toyama, K. Yasuda, H. Watanabe, A. Kimura, H. Muta, S. Yamanaka, Y.F. Li, Y. Satoh, S. Kano, H. Abe. Reassessment of oxidation-induced amorphization and dissolution of Nb precipitates in Zr-Nb nuclear fuel cladding tubes. Acta Materialia, 127 (2017) 153-164.
[6] Y. Matsukawa*, I. Okuma, H. Muta, Y. Shinohara, R. Suzue, H.L. Yang, T. Maruyama, T. Toyama, J.J. Shen, Y.F. Li, Y. Satoh, S. Yamanaka, H. Abe. Crystallographic analysis on atomic-plane parallelisms between bcc precipitates and hcp matrix in recrystallized Zr-2.5Nb alloys. Acta Materialia, 126 (2017) 86-101.
[7] Z. Zhao*, D. Kunii, T. Abe, H.L. Yang, S. Kano, Y. Matsukawa, Y. Satoh, H. Abe. Mechanical properties of Zircaloy-4 cladding tube by advanced expansion due to compression (A-EDC) test. Materials Transactions, 58 (2017) 46-51.
[8] H.L. Yang*, S. Kano, Z.G. Duan, Y. Matsukawa, K. Murakami, H. Abe, Study on microstructure and mechanical properties of dilute binary Zr-Nb model alloys for the applications of nuclear fuel cladding. Proceedings of 2017 International Congress on Advances in Nuclear Power
[9] S. Kano*, H.L. Yang, K. Murakami, H. Abe, Irradiation effects on localized deformation behaviors in Zr-Nb alloys. Proceedings of 2017 International Congress on Advances in Nuclear Power
[10] H.L. Yang*, Y. Matsukawa, S. Kano, Z.G. Duan, K. Murakami, H. Abe. Investigation on microstructural evolution and hardening mechanism in dilute Zr-Nb binary alloys. Journal of Nuclear Materials, 481 (2016) 117-124.
[11] H.L. Yang*, S. Kano, Y. Matsukawa, Y.F. Li, J.J. Shen, F. Li, Z.S. Zhao, Y. Satoh, H. Abe*. Effect of molybdenum on microstructures in Zr-1.2Nb alloys after β-quenching and subsequently 873 K annealing. Materials & Design, 104 (2016) 355-364.
[12] H.L. Yang*, S. Kano, Y. Matsukawa, Y.F. Li, J.J. Shen, Z.S. Zhao, F. Li, Y. Satoh, H. Abe*. Study on recrystallization and correlated mechanical properties in Mo-modified Zr-Nb alloys. Materials Science and Engineering: A, 661 (2016) 9-18.
[13] Y. Matsukawa*, H.L. Yang*, K. Saito, Y. Murakami, T. Maruyama, T. Iwai, K. Murakami, Y. Shinohara, T. Kido, T. Toyama, Z. Zhao, Y.F. Li, S. Kano, Y. Satoh, Y. Nagai, H. Abe. The effect of crystallographic mismatch on the obstacle strength of second phase precipitate particles in dispersion strengthening: bcc Nb particles and nanometric Nb clusters embedded in hcp Zr. Acta Materialia, 102 (2016) 323-332.
[14] S. Kano*, H. L. Yang, R. Suzue, Y. Matsukawa, Y. Satoh, H. Sakasegawa, H. Tanigawa, H. Abe. Precipitation of carbides in F82H steels and its impact on mechanical strength. Nuclear Materials and Energy, 9 (2016) 331-337.
[15] S. Kano*, A. Oba, H. L. Yang, Y. Matsukawa, Y. Satoh, H. Serizawa, H. Sakasegawa, H. Tanigawa, H. Abe. Microstructure and mechanical property in heat affected zone (HAZ) in F82H joined with SUS316L by fiber laser welding. Nuclear Materials and Energy, 9 (2016) 300-305.
[16] L.J. Chai*, B.F. Luan, B.F. Chen, H.L. Yang, Q. Liu, W.J. Huang. Concurrent inheritance of microstructure and texture after slow β→α cooling of commercially pure Zr. Science China Technological Sciences, 2016, 59 (11): 1771-1776.
[17] J.J. Shen*, Y.F. Li, F. Li, H.L. Yang, Z.S. Zhao, S. Kano, Y. Matsukawa, Y. Satoh, H. Abe. Microstructural characterization and strengthening mechanisms of a 12Cr-ODS steel. Materials Science and Engineering: A, 673 (2016) 624-632.
[18] Y.F. Li*, J.J. Shen, F. Li, H.L. Yang, S. Kano, Y. Matsukawa, H.Y. Fu, Y. Satoh, H. Abe, T. Moroga. Effects of fabrication processing on the microstructure and mechanical properties of oxide dispersion strengthening steels. Materials Science and Engineering: A, 654 (2016) 203-212.
[19] S. Kano*, A. Oba, H. L. Yang, Y. Matsukawa, Y. Saton, H. Serizawa, H. Sakasegawa, H. Tanigawa, H. Abe. Experimental assessment of temperature distribution in heat affected zone (HAZ) in dissimilar joint between 8Cr-2W steel and SUS316L fabricated by 4 kW fiber laser welding. Mechanical Engineering Letters, 2 (2016), 1-9.
[20] H.L. Yang*, S. Kano, J. Shen, Z. Zhao, Y. Matsukawa, Y. Satoh, H. Abe. Investigation on recrystallization characteristics and mechanical properties of Zr-Nb-Mo ternary alloys. Proceedings of The Ninth Pacific Rim International Conference on Advanced Materials and Processing.
[21] J. Shen*, H.L. Yang, Y. Li, S. Kano, Y. Matsukawa, Y. Satoh, H. Abe. Microstructural stability of an as-fabricated 12Cr-ODS steel under elevated-temperature annealing. Proceedings of The Ninth Pacific Rim International Conference on Advanced Materials and Processing.
[22] S. Kano*, A. Kobayashi, H.L. Yang, D. Kunii, Z. Zhao, K. Murakami, H. Abe. Deformation microstructure in Zr-Nb alloys under uniaxial tensile and advanced expansion due to compression tests. Proceedings of The Ninth Pacific Rim International Conference on Advanced Materials and Processing.
[23] Z. Zhao*, D. Kunii, H.L. Yang, S. Kano, Y. Matsukawa, Y. Satoh, H. Abe. Hydride-induced ductility loss in the hoop and axial directions of Zr-2.5Nb cladding tube. Proceedings of The Ninth Pacific Rim International Conference on Advanced Materials and Processing.
[24] H.L. Yang*, J.J. Shen, S. Kano, Y. Matsukawa, Y.F. Li, Y. Satoh, T. Matsunaga, H. Abe. Effects of Mo addition on precipitation in Zr-1.2Nb alloys. Materials Letters, 158 (2015) 88-91.
[25] H.L. Yang*, H. Abe, S. Kano, Y. Matsukawa, Y. Satoh. Effects of molybdenum on microstructural evolution and mechanical properties in Zr-Nb alloys as nuclear fuel cladding materials. Journal of Nuclear Science and Technology, 52 (2015)1265-1273.
[26] H.L. Yang*, J.J. Shen, Y. Matsukawa, Y. Satoh, S. Kano, Z. Zhao, Y. Li, F. Li, H. Abe. Effects of alloying elements (Sn, Nb, Cr, and Mo) on the microstructure and mechanical properties of zirconium alloys. Journal of Nuclear Science and Technology, 52 (2015) 1162-1173.
[27] H. Abe*, T. Abe, S. Kishita, S. Kano, Y. Li, H.L. Yang, K. Tawara, Y. Matsukawa, Y. Satoh. Development of advanced expansion due to compression (A-EDC) test method for safety evaluation of degraded nuclear fuel cladding materials. Journal of Nuclear Science and Technology, 52 (2015) 1232-1239.
[28] H.L. Yang* H. Abe, Y. Matsukawa, Y. Satoh, S. Kano. Characterization of hydrogenation behavior on Mo-modified Zr-Nb alloys as nuclear fuel cladding materials. Proceedings of 2014 Water Reactor Fuel Meeting.

Nuclear Materials and Energy, Early Career Editorial Board Member
International Journal of Advanced Nuclear Reactor Design and Technology, Young Editorial Board Member
Tungsten, Young Editorial Board Member

2022, Journal of Nuclear Materials, Rising Stars in Nuclear Materials Award
2021, Journal of Nuclear Science and Technology, Most Cited Article Award 2021
2019, 日本原子力学会材料部会 Best Figure Award
2016, 日本原子力学会，核燃料部会部会奖
2016, The Ninth Pacific Rim International Conference on Advanced Materials and Processing, Best Poster Award
2014, 日本原子力学会核燃料部会, Best Presentation Award