Akihiko Kimura

Professor, Em

Kyoto University

Japan

Research Interests

Explore related searches

Professors in Japan

Contact this professor

Get a free first email built on one of their papers, ready for you to edit and send yourself.

About

Akihiko Kimura is a Professor at Kyoto University in Japan. His research areas include alloy design, materials characterization, and the study of radiation effects in steels, particularly in the context of accident-tolerant fuel cladding for boiling water reactors (BWRs). He has contributed to numerous articles addressing the microstructural evolution and mechanical properties of various materials under radiation and corrosion conditions.

Articles (10)

Year:

2023

Year:

2023

Year:

2023

Year:

2022

Year:

2022

Year:

2021

Year:

2021

Year:

2021

Year:

2021

Year:

2021

Collaborators (4)

Kan Sakamoto

Chief Researcher

Nippon Steel Technology Co.,Ltd.

JAPAN

View details

Shinji Fujimoto

Professor

Osaka University

JAPAN

View details

Hiroaki Tsuchiya

Osaka University

JAPAN

View details

Masato Yamashita

Guest Professor

Osaka University

JAPAN

View details

ApplyKite TwinLearns as you apply

Make your next move.

Prepare your application

Review drafts before you send them.

Akihiko Kimura

Research Interests

Explore related searches

Contact this professor

About

Articles (10)

Alloy design and characterization of a recrystallized FeCrAl-ODS cladding for accident-tolerant BWR fuels: An overview of research activity in Japan

Cavity evolution and void swelling in dual ion irradiated tempered martensitic steels

Twofold age-hardening mechanism of Al-added high-Cr ODS ferritic steels

A comparison study of change in hardness and microstructures of a Zr-added FeCrAl ODS steel irradiated with heavy ions

Evaluating the irradiation hardening of reactor pressure vessel steels by nanoindentation hardness test and micropillar compression test

Corrosion behavior of carbon steel coated with a zinc‐rich paint containing metallic compounds under wet and dry cyclic conditions

Development of accident tolerant FeCrAl-ODS fuel cladding for BWRs in Japan

Hardening of high-energy self-ion irradiated FeCrAl ODS alloys evaluated by micro- and nano-hardness tests

Microstructure and mechanical properties of HAZ of RPVS clad with duplex stainless steel

Radiation embrittlement of clad-HAZ of RPV of a decommissioned BWR plant

Collaborators (4)

Kan Sakamoto

Shinji Fujimoto

Hiroaki Tsuchiya

Masato Yamashita

Make your next move.