R&D plan for development of oxidation-resistant graphite and investigation of oxidation behavior of SiC coated fuel particle to enhance safety of HTGR
Ueta, Shohei, Sumita, Junya, Shibata, Taiju, Aihara, Jun, Fujita, Ichiro, Ohashi, Jun, Nagaishi, Yoshihide, Muto, Takenori, Sawa, Kazuhiro, Sakaba, Nariaki
Published in Nuclear engineering and design (01.05.2014)
Published in Nuclear engineering and design (01.05.2014)
Get full text
Journal Article
Investigation of Microstructural Change by X-ray Tomography and Anisotropic Effect on Thermal Property of Thermally Oxidized 2D-C/C Composite for Very High Temperature Reactor
SUMITA, Junya, SHIVARA, Taiju, KUNIMOTO, Eiji, YAMAJI, Masatoshi, KONISHI, Takashi, SAWA, Kazuhiro
Published in Journal of nuclear science and technology (01.04.2010)
Published in Journal of nuclear science and technology (01.04.2010)
Get full text
Journal Article
Development of an Evaluation Model for the Thermal Annealing Effect on Thermal Conductivity of IG-110 Graphite for High-Temperature Gas-Cooled Reactors
SUMITA, Junya, SHIBATA, Taiju, NAKAGAWA, Shigeaki, IYOKU, Tatsuo, SAWA, Kazuhiro
Published in Journal of nuclear science and technology (01.07.2009)
Published in Journal of nuclear science and technology (01.07.2009)
Get full text
Journal Article
Prediction of Fuel Performance and Fission Gas Release Behavior during Normal Operation of the High Temperature Engineering Test Reactor by JAERI and FZJ Modeling Approach
SAWA, Kazuhiro, UETA, Shouhei, SUMITA, Junya, VERFONDERN, Karl
Published in Journal of nuclear science and technology (01.06.2001)
Published in Journal of nuclear science and technology (01.06.2001)
Get full text
Journal Article
HTTR-GT/H2 test plant – System performance evaluation for HTTR gas turbine cogeneration plant
Sato, Hiroyuki, Nomoto, Yasunobu, Horii, Shoichi, Sumita, Junya, Yan, Xing L
Published in Nuclear engineering and design (01.04.2018)
Published in Nuclear engineering and design (01.04.2018)
Get full text
Journal Article
Integrity Confirmation Tests and Post-irradiation Test Plan of the HTTR First-Loading Fuel
SAWA, Kazuhiro, SUMITA, Junya, UETA, Shouhei, SUZUKI, Shuichi, TOBITA, Tsutomu, SAITO, Takashi, MINATO, Kazuo, KOYA, Toshio, SEKINO, Hajime
Published in Journal of nuclear science and technology (01.06.2001)
Published in Journal of nuclear science and technology (01.06.2001)
Get full text
Journal Article
Design of HTTR-GT/H2 test plant
Yan, Xing L., Sato, Hiroyuki, Sumita, Junya, Nomoto, Yasunobu, Horii, Shoichi, Imai, Yoshiyuki, Kasahara, Seiji, Suzuki, Koichi, Iwatsuki, Jin, Terada, Atsuhiko, Tachibana, Yukio, Oono, M., Yamada, S., Suyama, Kazumasa
Published in Nuclear engineering and design (01.04.2018)
Published in Nuclear engineering and design (01.04.2018)
Get full text
Journal Article
Evaluation of fracture toughness of fine-grained isotropic graphites for HTGR
Yamada, Teruaki, Matsushima, Yuki, Kuroda, Masatoshi, Sumita, Junya, Shibata, Taiju, Fujita, Ichiro, Sawa, Kazuhiro
Published in Nuclear engineering and design (01.05.2014)
Published in Nuclear engineering and design (01.05.2014)
Get full text
Journal Article
Principle Design of Graphite Components for HTTR and R&D on Nuclear Graphite for HTGR in JAEA
Shibata, Taiju, Sumita, Junya, Nishihara, Tetsuo, Iyoku, Tatsuo, Ishihara, Masahiro
Published in Key Engineering Materials (01.07.2016)
Published in Key Engineering Materials (01.07.2016)
Get full text
Journal Article
Development of evaluation method with X-ray tomography for material property of IG-430 graphite for VHTR/HTGR
Sumita, Junya, Shibata, Taiju, Fujita, Ichiro, Kunimoto, Eiji, Yamaji, Masatoshi, Eto, Motokuni, Konishi, Takashi, Sawa, Kazuhiro
Published in Nuclear engineering and design (01.05.2014)
Published in Nuclear engineering and design (01.05.2014)
Get full text
Journal Article
Design of HTTR-GT/H^sub 2^ test plant
Yan, Xing L, Sato, Hiroyuki, Sumita, Junya, Nomoto, Yasunobu, Horii, Shoichi, Imai, Yoshiyuki, Kasahara, Seiji, Suzuki, Koichi, Iwatsuki, Jin, Terada, Atsuhiko, Tachibana, Yukio, Oono, M, Yamada, S, Suyama, Kazumasa
Published in Nuclear engineering and design (01.04.2018)
Get full text
Published in Nuclear engineering and design (01.04.2018)
Journal Article
Development of non-destructive evaluation methods for degradation of HTGR graphite components
Shibata, Taiju, Sumita, Junya, Tada, Tatsuya, Sawa, Kazuhiro
Published in Journal of nuclear materials (31.10.2008)
Published in Journal of nuclear materials (31.10.2008)
Get full text
Journal Article
Non-destructive evaluation methods for degradation of IG-110 and IG-430 graphite
Shibata, Taiju, Sumita, Junya, Tada, Tatsuya, Hanawa, Satoshi, Sawa, Kazuhiro, Iyoku, Tatsuo
Published in Journal of nuclear materials (31.10.2008)
Published in Journal of nuclear materials (31.10.2008)
Get full text
Journal Article
Development of an Evaluation Model for the Thermal Annealing Effect on Thermal Conductivity of IG-110 Graphite for High-Temperature Gas-Cooled Reactors
SUMITA, Junya, SHIBATA, Taiju, NAKAGAWA, Shigeaki, IYOKU, Tatsuo, SAWA, Kazuhiro
Published in Journal of nuclear science and technology (01.07.2009)
Published in Journal of nuclear science and technology (01.07.2009)
Get full text
Journal Article