关注
Hiroshi Oka
Hiroshi Oka
在 eng.hokudai.ac.jp 的电子邮件经过验证
标题
引用次数
引用次数
年份
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
642011
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
612011
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
582017
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
532013
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
412014
Study on irradiation effects of refractory bcc high-entropy alloy
Y Zong, N Hashimoto, H Oka
Nuclear Materials and Energy 31, 101158, 2022
372022
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
372014
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
222016
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
202019
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
142022
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
112015
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
102022
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
102021
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
102016
Selective growth of noble gases at metal/oxide interface
K Takahashi, H Oka, S Ohnuki
ACS applied materials & interfaces 8 (6), 3725-3729, 2016
72016
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
72011
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
52018
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
42022
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
42022
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
42013
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