In situ observation of damage structure in ODS austenitic steel during electron irradiation H Oka, M Watanabe, H Kinoshita, T Shibayama, N Hashimoto, S Ohnuki, ... Journal of Nuclear Materials 417 (1-3), 279-282, 2011 | 64 | 2011 |
Development of damage structure in 16Cr–4Al ODS steels during electron-irradiation CZ Yu, H Oka, N Hashimoto, S Ohnuki Journal of Nuclear Materials 417 (1-3), 286-288, 2011 | 61 | 2011 |
Ultra-high temperature tensile properties of ODS steel claddings under severe accident conditions Y Yano, T Tanno, H Oka, S Ohtsuka, T Inoue, S Kato, T Furukawa, ... Journal of Nuclear Materials 487, 229-237, 2017 | 58 | 2017 |
Morphology of oxide particles in ODS austenitic stainless steel H Oka, M Watanabe, N Hashimoto, S Ohnuki, S Yamashita, S Ohtsuka Journal of Nuclear Materials 442 (1-3), S164-S168, 2013 | 53 | 2013 |
Effects of milling process and alloying additions on oxide particle dispersion in austenitic stainless steel H Oka, M Watanabe, S Ohnuki, N Hashimoto, S Yamashita, S Ohtsuka Journal of Nuclear Materials 447 (1-3), 248-253, 2014 | 41 | 2014 |
Study on irradiation effects of refractory bcc high-entropy alloy Y Zong, N Hashimoto, H Oka Nuclear Materials and Energy 31, 101158, 2022 | 37 | 2022 |
A metal-oxide catalyst enhanced the desorption properties in complex metal hydrides T Zhang, S Isobe, Y Wang, H Oka, N Hashimoto, S Ohnuki Journal of Materials Chemistry A 2 (12), 4361-4365, 2014 | 37 | 2014 |
Effect of thermo-mechanical treatments on nano-structure of 9Cr-ODS steel H Oka, T Tanno, S Ohtsuka, Y Yano, T Uwaba, T Kaito, M Ohnuma Nuclear Materials and Energy 9, 346-352, 2016 | 22 | 2016 |
Ultra-high temperature creep rupture and transient burst strength of ODS steel claddings Y Yano, Y Sekio, T Tanno, S Kato, T Inoue, H Oka, S Ohtsuka, T Furukawa, ... Journal of Nuclear Materials 516, 347-353, 2019 | 20 | 2019 |
Effect of stacking fault energy on irradiation damage in reduced activation high entropy alloys N Hashimoto, E Wada, H Oka Journal of Nuclear Materials 566, 153767, 2022 | 14 | 2022 |
Evaluation of multi-layered hardness in ion-irradiated stainless steel by nano-indentation technique H Oka, Y Sato, N Hashimoto, S Ohnuki Journal of Nuclear Materials 462, 470-474, 2015 | 11 | 2015 |
Effect of Al on oxidation behavior of AlxCrCuFeNi2 (x= 0.2, 0.4, 0.6) high entropy alloys P Bi, N Hashimoto, S Hayashi, H Oka, S Isobe Corrosion Science 208, 110697, 2022 | 10 | 2022 |
Microstructural stability of ODS steel after very long-term creep test H Oka, T Tanno, Y Yano, S Ohtsuka, T Kaito, Y Tachi Journal of Nuclear Materials 547, 152833, 2021 | 10 | 2021 |
Strength anisotropy of rolled 11Cr-ODS steel T Tanno, Y Yano, H Oka, S Ohtsuka, T Uwaba, T Kaito Nuclear Materials and Energy 9, 353-359, 2016 | 10 | 2016 |
Selective growth of noble gases at metal/oxide interface K Takahashi, H Oka, S Ohnuki ACS applied materials & interfaces 8 (6), 3725-3729, 2016 | 7 | 2016 |
Characterization of oxide particles in ODS austenitic stainless steel after heavy ion irradiation up to high doses H Oka, Y Yamazaki, H Kinoshita, N Hashimoto, S Ohnuki, S Yamashita, ... MRS Online Proceedings Library 1298, 21-25, 2011 | 7 | 2011 |
Effect of nitrogen concentration on nano-structure and high-temperature strength of 9Cr-ODS steel H Oka, T Tanno, S Ohtsuka, Y Yano, T Kaito Nuclear Materials and Energy 16, 230-237, 2018 | 5 | 2018 |
Effect of nitrogen concentration on creep strength and microstructure of 9Cr-ODS ferritic/martensitic steel H Oka, T Tanno, Y Yano, S Ohtsuka, T Kaito, N Hashimoto Journal of Nuclear Materials 572, 154032, 2022 | 4 | 2022 |
Improvement of thermal conductivity by adding tungsten and/or copper wire in F82H J Heo, N Hashimoto, H Oka, H Noto Journal of Nuclear Science and Technology 59 (2), 216-221, 2022 | 4 | 2022 |
Irradiation effect on tensile property of F82H IEA and its joint in TITAN project N Hashimoto, H Oka, T Muroga, T Nagasaka, A Kimura, S Ukai, ... Materials Transactions 54 (4), 442-445, 2013 | 4 | 2013 |