Author

Hiromasa Nishioka

Observed names: H. Nishioka, Hiromasa NISHIOKA, 弘雅西岡, 西岡弘雅

Observed institutions: Kansai Electric Power (Japan), Institute of Nuclear Safety System, Inc. (Japan)

OpenAlex ID: A5036024949

Evolution of Microstructure and Microchemistry in Cold-worked 316 Stainless Steels under PWR Irradiation

2006 · Koji FUKUYA, Katsuhiko FUJII, et al. · Journal of Nuclear Science and Technology · 101

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Deformation Structure in Highly Irradiated Stainless Steels

2008 · Hiromasa NISHIOKA, Koji FUKUYA, et al. · Journal of Nuclear Science and Technology · 56

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IASCC Initiation in Highly Irradiated Stainless Steels under Uniaxial Constant Load Conditions

2008 · Hiromasa NISHIOKA, Koji FUKUYA, et al. · Journal of Nuclear Science and Technology · 47

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Fracture behavior of austenitic stainless steels irradiated in PWR

2008 · K. Fukuya, H. Nishioka, et al. · Journal of Nuclear Materials · 43

Degradation of Grain Boundary Strength by Oxidation in Alloy 600

2011 · Katsuhiko Fujii, Terumitsu Miura, et al. · Springer eBooks · 36

An EBSD examination of SUS316 stainless steel irradiated to 73dpa and deformed at 593K

2011 · Koji Fukuya, Hiromasa Nishioka, et al. · Journal of Nuclear Materials · 31

Local strain distribution near grain boundaries under tensile stresses in highly irradiated SUS316 stainless steel

2012 · Koji Fukuya, Hiromasa Nishioka, et al. · Journal of Nuclear Materials · 24

Effects of hydrogen on interaction between dislocations and radiation-induced defects in austenitic stainless steels

2013 · Terumitsu Miura, Katsuhiko Fujii, et al. · Journal of Nuclear Materials · 17

Degradation of Grain Boundary Strength by Oxidation in Alloy 600

2012 · Katsuhiko Fujii, Terumitsu Miura, et al. · Wiley eBooks · 17

A prediction model of IASCC initiation stress for bolts in PWR core internals

2009 · Koji Fukuya, Katsuhiko Fujii, et al. · Nuclear Engineering and Design · 14

Effects of Dissolved Hydrogen and Strain Rate on IASCC Behavior in Highly Irradiated Stainless Steels

2008 · Koji FUKUYA, Hiromasa NISHIOKA, et al. · Journal of Nuclear Science and Technology · 13

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Total evaluation of in bundle void fraction measurement test of PWR fuel assembly

1996 · Keiichi HORI, Keiji MIYAZAKI, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 5

Effects of dissolved hydrogen on IASCC behavior

2011 · K Fuji, Hiromasa Nishioka, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 2

Analyses of Surface Oxides Formed on Irradiated Stainless Steels in Simulated PWR Primary Water

2012 · 弘雅西岡, 耕司福谷, et al. · 1

An expert system for PWR core operation management

1988 · Toshio Ida, Masahiro Masuda, et al. · Transactions of the American Nuclear Society · 1

照射ステンレス鋼の粒界破壊に及ぼすHe影響の検討(その2)照射誘起偏析との重畳効果

2014 · 照光三浦, 克彦藤井, et al.

ステンレス鋼の軽水炉照射挙動 = Irradiation Behavior of Stainless Steels in Light Water Reactors

2009 · 耕司福谷, 西岡弘雅, et al.

PWR Zr’y -4被覆管の水素化物応力再配向特性に関する検討

2003 · 西岡弘雅, 千田康英, et al. · 日本原子力学会　年会・大会予稿集 2003年秋の大会

Plutonium recycling experience in Japanese PWRs

1992 · Hiromasa Nishioka, Shigemitsu Suzuki, et al. · Transactions of the American Nuclear Society

Works count: 19

Citation count: 408

H-index: 11

I10-index: 11