Selected Publications
2023
[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
[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. (2022 Journal of Nuclear Materials 'Rising Star Awards')
[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
[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 stdudy, 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-radiationr 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
[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
[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} twnsile 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 strenghthed 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 Engieering 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
[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 ineraction between (Fe, Cr) oxides and Mo oxide at high temperature for self-healing intelligence on nuclear fuel cladding in LWRs, Journal of Nuclaer 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 Technoglogy, 334 (2018) 319-327.
Earlier than 2018
[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 Ziecaloy-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.
