Tadahiko TORIMARU - Concepedia

Author

Tadahiko TORIMARU

Hokkaido University

Also Known As

T Torimaru, T. Torimaru, Tadahiko TORIMARU, Tadahiko Torimaru

Publications

579

Citations

H-Index

Concepts

All Affiliations

Hokkaido University Japan Atomic Energy Agency Kyoto University Tokyo Institute of Technology Tomsk State University of Control Systems and Radio-Electronics

About

Tadahiko TORIMARU is an author at Hokkaido University specializing in corrosion, microstructure, and materials science.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	11	13	457
2	Materials Science	11	12	412
3	Materials Engineering	9	9	292
4	Chemical Engineering	6	6	184
5	Applied Physics	2	2	87

Tadahiko TORIMARU

Publications

550

Citations

H-Index

Page 1

	Year	Citations
Separation of Microstructural and Microchemical Effects in Irradiation Assisted Stress Corrosion Cracking using Post-irradiation Annealing Koji Fukuya, Morihito NAKANO, Katsuhiko Fujii, Journal of Nuclear Science and Technology Materials ScienceCorrosion TechnologyChemical EngineeringCorrosion ProtectionEngineering	2004	59
Ultra-high temperature tensile properties of ODS steel claddings under severe accident conditions Yasuhide Yano, Takashi Tanno, Hiroshi Oka, Journal of Nuclear Materials Materials ScienceSevere Accident ConditionsEngineeringSuperalloyOds Steel Claddings	2017	59
Growth of oxide particles in FeCrAl- oxide dispersion strengthened steels at high temperature Naoko Oono, Shigeharu Ukai, Shigenari Hayashi, Journal of Nuclear Materials Materials EngineeringMaterials ScienceOxide ParticlesEngineeringMechanical Engineering	2017	55
IASCC Susceptibility and Slow Tensile Properties of Highly-irradiated 316 Stainless Steels Koji Fukuya, Morihito NAKANO, Katsuhiko Fujii, Journal of Nuclear Science and Technology EngineeringMechanical EngineeringSlow Tensile TestsHigh Strength Low Alloy SteelStress Corrosion Cracking	2004	54
Effect of Cr/Al contents on the 475 º C age-hardening in oxide dispersion strengthened ferritic steels Wentuo Han, Kiyohiro Yabuuchi, Akihiko Kimura, Nuclear Materials and Energy	2016	49
IASCC Initiation in Highly Irradiated Stainless Steels under Uniaxial Constant Load Conditions Hiromasa Nishioka, Koji Fukuya, Katsuhiko Fujii, Journal of Nuclear Science and Technology Materials EngineeringNeutron DoseEngineeringHigh Temperature MaterialsCorrosion	2008	45
Changes in mechanical properties of irradiated Zircaloy-2 fuel cladding due to short term annealing Tadahiko TORIMARU, Takayoshi Yasuda, Masafumi NAKATSUKA Journal of Nuclear Materials Materials ScienceMaterials EngineeringNuclear CeramicEngineeringMechanical Properties	1996	39
Fracture behavior of austenitic stainless steels irradiated in PWR K. Fukuya, Hiromasa Nishioka, Katsushi Fujii, Journal of Nuclear Materials Materials ScienceEngineeringRadiation Materials ScienceHigh Strength Low Alloy SteelFracture Behavior	2008	36
Role of Radiation-Induced Grain Boundary Segregation in Irradiation Assisted Stress Corrosion Cracking Koji Fukuya, Morihito NAKANO, Katsuhiko Fujii, Journal of Nuclear Science and Technology Materials ScienceMaterials EngineeringChemical EngineeringScc SusceptibilityEngineering	2004	34
Oxide particle coarsening at temperature over 1473 K in 9CrODS steel Naoko Oono, Kazuyuki Nakamura, Shigeharu Ukai, Nuclear Materials and Energy	2016	30

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