Hiroyasu Tanigawa

National Institutes for Quantum Science and Technology — Japan

Materials Science · Physical Sciences

40h-index6.4kcitations302works2.82yr avg
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Research Topics

Fusion materials and technologies(215), Nuclear Materials and Properties(149), Microstructure and Mechanical Properties of Steels(53), Fatigue and fracture mechanics(37), Nuclear reactor physics and engineering(35)

Publications301 total

Preliminary structural design of WCCB TBM-set
Fusion Engineering and Design·2025· 1 cited
Thermal properties of plasma-sintered Be12Ti
Fusion Engineering and Design·2025
Deuterium retention properties and bubble behaviors of Be12Ti after irradiation with D+ at high temperature
Fusion Engineering and Design·2025Open Access
Research on pebble characterizations and gas pressure in Li2TiO3 pebbles bed
Fusion Engineering and Design·2025
Contributors
Elsevier eBooks·2024Open Access
Status and future development of Japanese reduced activation ferritic/martensitic steel F82H
Elsevier eBooks·2024
Determining reference standard strength for neutron-irradiated reduced activation ferritic/martensitic steel F82H by Bayesian method
Journal of Nuclear Materials·2024Open Access
TEM-EELS analysis reveals the W-atom mediated radiation-induced amorphization in M23C6
Journal of Nuclear Materials·2024· 3 cited
Effect of helium on micro-fracture strength for multi-ion-irradiated F82H by micro-tensile testing
Nuclear Materials and Energy·2024· 2 citedOpen Access
Tensile and creep properties of small specimens of reduced-activation ferritic steel F82H, and the correlation to standard specimen data
Nuclear Science and Technology Open Research·2024Open Access
W-concentration dependent radiation-induced amorphization in M23C6 via atomic-scale analysis by Voronoi tessellation
Materialia·2024· 2 cited
Status of the ITER TBM Program and overview of its technical objectives
Fusion Engineering and Design·2024· 22 cited
Blanket test facility for mockup testing on water cooled ceramic breeder blanket system
Fusion Engineering and Design·2024
Size dependence of micro-scale mechanical properties on heavy-ion irradiated tempered-martensitic steel evaluated through nanoindentation and micropillar compression tests
Journal of Nuclear Materials·2024· 7 citedOpen Access
Transmission electron microscopy study of the radiation-induced amorphization in the Cr-W-C ternary M23C6
Journal of Nuclear Materials·2024· 4 cited
Overview of progress on water cooled ceramic breeder blanket in Japan
Fusion Engineering and Design·2024· 10 cited
Functional tests for water cooled ceramic breeder blanket system using full-scale mockups
Fusion Engineering and Design·2024· 2 cited
Ductility evaluation for small plate specimens by fracture surface shape change
Fusion Engineering and Design·2024· 1 cited
Tensile and creep test data of reduced-activation ferritic steel F82H using small specimens and the standard specimen for comparison study
Figshare·2024· 1 citedOpen Access
Determining Reference Standard Strength for Neutron-Irradiated Reduced Activation Ferritic/Martensitic Steel F82h by Bayesian Method
SSRN Electronic Journal·2024Open Access
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Frequent Co-authors

Takanori Hirose(13), Hideo Sakasegawa(13), Masami Ando(12), S. Jitsukawa(10), A. Kohyama(8), Yutai Katoh(7), Akihiko Kimura(6), G.R. Odette(6), Mikio Enoeda(6), Takashi Nozawa(6), S.J. Zinkle(5), R. Lindau(5), Mikhail A. Sokolov(5), K. Ezato(5), Ryuta Kasada(5), R.L. Klueh(5), Dai Hamaguchi(5), Satoshi Ohtsuka(5), Richard J. Kurtz(4), R.E. Stoller(4)