Ryuta Kasada

发表

Japanese endeavors to establish technological bases for DEMO

Hisashi Tanigawa, Hiroshi Yamada, Ryuta Kasada, 2016 .

Development of Strategic Establishment of Technology Bases for a Fusion DEMO Reactor in Japan

Hisashi Tanigawa, Kenji Tobita, Ryuta Kasada, 2016 .

Let's Create our Future with Fusion Reactor

Ryuta Kasada, 2016 .

Fusion materials development program in the broader approach activities

Takashi Nozawa, Akira Kohyama, Anton Möslang, 2009 .

An action plan of Japan toward development of demo reactor

Kyoko Oba, Yasushi Ikebe, Mieko Kashiwagi, 2018 .

Report by the Joint-Core Team for the Establishment of Technology Bases Required for the Development of a Fusion DEMO Reactor: Basic Concept of DEMO and Structure of Technological Issues

Hisashi Tanigawa, Hiroshi Yamada, Kenji Tobita, 2015 .

Past and Future of Nuclear Fusion Engineering

Ryuta Kasada, 2019 .

A system dynamics model for stock and flow of tritium in fusion power plant

Satoshi Konishi, Ryuta Kasada, Kenji Tobita, 2015 .

Neutronics of SiC-LiPb High Temperature Blanket for Tritium Production

Satoshi Konishi, Ryuta Kasada, Saerom Kwon, 2013 .

Characterization of Mechanically Alloyed Powders for High-Cr Oxide Dispersion Strengthened Ferritic Steel

Ryuta Kasada, Shigeharu Ukai, Masaki Inoue, 2009 .

Annealing behavior of irradiation hardening and microstructure in helium-implanted reduced activation martensitic steel

Ryuta Kasada, Akira Hasegawa, Hideki Matsui, 2000 .

Myth of initial loading tritium for DEMO—Modelling of fuel system and operation scenario

Satoshi Konishi, Ryuta Kasada, Fumito Okino, 2017 .

Evaluation of irradiation hardening of ion-irradiated V-4Cr-4Ti and V-4Cr-4Ti-0.15Y alloys by nanoindentation techniques

Ryuta Kasada, Takeshi Miyazawa, Takeo Muroga, 2014 .

Evaluation of Helium effects on swelling behavior of oxide dispersion strengthened ferritic steels under ion irradiation

Ryuta Kasada, Kentaro Yutani, Hirotatsu Kishimoto, 2007 .

Specimen size effects on fracture toughness of JLF-1 reduced-activation ferritic steel

Ryuta Kasada, A. Kimura, A. Kimura, 2004 .

Effect of helium implantation on mechanical properties and microstructure evolution of reduced-activation 9Cr–2W martensitic steel

Ryuta Kasada, Akira Hasegawa, A. Hasegawa, 2001 .

Irradiation-Induced Hardening and Embrittlement of High-Cr ODS Ferritic Steels

Ryuta Kasada, J. Lee, A. Kimura, 2009 .

A new approach to evaluate irradiation hardening of ion-irradiated ferritic alloys by nano-indentation techniques

Ryuta Kasada, Akihiko Kimura, A. Kimura, 2011 .

Underwater explosive welding of tungsten to reduced-activation ferritic steel F82H

Satoshi Konishi, Ryuta Kasada, Daichi Mori, 2014 .

Development of Al added high-Cr ODS steels for fuel cladding of next generation nuclear systems

N. Muthukumar, Ryuta Kasada, Shigeharu Ukai, 2011 .

Assessment of Neutron Irradiation-Induced Grain Boundary Embrittlement by Phosphorous Segregation in a Reactor Pressure Vessel Steel

Katsuhiko Fujii, Ryuta Kasada, Masaaki Shibata, 2005 .

Grain Boundary Phosphorus Segregation in Thermally Aged Low Alloy Steels

Katsuhiko Fujii, Ryuta Kasada, Akihiko Kimura, 2006 .

Enhanced Mass Transfer of Deuterium Extracted from Falling Liquid Pb-17Li Droplets

Satoshi Konishi, Ryuta Kasada, Fumito Okino, 2013 .

Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules

Steven J. Zinkle, Hisashi Serizawa, Eiichi Wakai, 2008 .