Reactivity control system of the high temperature engineering test reactor
Tachibana, Yukio, Sawahata, Hiroaki, Iyoku, Tatsuo, Nakazawa, Toshio
Published in Nuclear engineering and design (01.10.2004)
Published in Nuclear engineering and design (01.10.2004)
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
Operation and maintenance experience from the HTTR database
Shimizu, Atsushi, Furusawa, Takayuki, Homma, Fumitaka, Inoi, Hiroyuki, Umeda, Masayuki, Kondo, Masaaki, Isozaki, Minoru, Fujimoto, Nozomu, Iyoku, Tatsuo
Published in Journal of nuclear science and technology (02.12.2014)
Published in Journal of nuclear science and technology (02.12.2014)
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
Development of Thermal/Irradiation Stress Analytical Code "VIENUS" for HTTR Graphite Block
IYOKU, Tatsuo, ISHIHARA, Masahiro, SHIRAI, Hiroshi
Published in Journal of nuclear science and technology (01.10.1991)
Published in Journal of nuclear science and technology (01.10.1991)
Get full text
Journal Article
Structural design of high temperature metallic components: Japan's HTTR. Japan's first High Temperature Engineering Test Reactor of JAERI, its design, its components, its safety features, its planned experiments and its industrial applications, including Japan's concept of future HTRs
Get full text
Journal Article
Principle design and data of graphite components
Ishihara, Masahiro, Sumita, Junya, Shibata, Taiju, Iyoku, Tatsuo, Oku, Tatsuo
Published in Nuclear engineering and design (01.10.2004)
Published in Nuclear engineering and design (01.10.2004)
Get full text
Journal Article
Non-destructive evaluation methods for degradation of IG-110 and IG-430 graphite: Proceedings of the Seventh and Eighth International Graphite Specialists Meetings (INGSM)
SHIBATA, Taiju, SUMITA, Junya, TADA, Tatsuya, HANAWA, Satoshi, SAWA, Kazuhiro, IYOKU, Tatsuo
Published in Journal of nuclear materials (2008)
Get full text
Published in Journal of nuclear materials (2008)
Journal Article
High-Temperature Continuous Operation of the HTTR
TAKAMATSU, Kuniyoshi, SAWA, Kazuhiro, KUNITOMI, Kazuhiko, HINO, Ryutaro, OGAWA, Masuro, KOMORI, Yoshihiro, NAKAZAWA, Toshio, IYOKU, Tatsuo, FUJIMOTO, Nozomu, NISHIHARA, Tetsuo, SHINOZAKI, Masayuki
Published in Nihon Genshiryoku Gakkai wabun ronbunshi = Transactions of the Atomic Energy Society of Japan (01.01.2011)
Published in Nihon Genshiryoku Gakkai wabun ronbunshi = Transactions of the Atomic Energy Society of Japan (01.01.2011)
Get full text
Journal Article
Nuclear Characteristics of High Temperature Engineering Test Reactor (HTTR)
Iigaki, Kazuhiko, Goto, Minoru, Tachibana, Yukio, Iyoku, Tatsuo, Komori, Yoshihiro
Published in Koon Gakkaishi (01.01.2006)
Get full text
Published in Koon Gakkaishi (01.01.2006)
Journal Article
Design of core components
Iyoku, Tatsuo, Ueta, Shohei, Sumita, Junya, Umeda, Masayuki, Ishihara, Masahiro
Published in Nuclear engineering and design (01.10.2004)
Published in Nuclear engineering and design (01.10.2004)
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
Reactor pressure vessel design of the high temperature engineering test reactor: Japan's HTTR. Japan's first High Temperature Engineering Test Reactor of JAERI, its design, its components, its safety features, its planned experiments and its industrial applications, including Japan's concept of future HTRs
TACHIBANA, Yukio, NAKAGAWA, Shigeaki, IYOKU, Tatsuo
Published in Nuclear engineering and design (2004)
Get full text
Published in Nuclear engineering and design (2004)
Journal Article
R&D on core seismic design
Iyoku, Tatsuo, Smita, Junya, Ishihara, Masahiro, Ueta, Shohei
Published in Nuclear engineering and design (01.10.2004)
Published in Nuclear engineering and design (01.10.2004)
Get full text
Journal Article
Reactivity control system of the high temperature engineering test reactor
Tachibana, Yukio, Sawahata, Hiroaki, Iyoku, Tatsuo, Nakazawa, Toshio
Published in Nuclear engineering and design (01.10.2004)
Published in Nuclear engineering and design (01.10.2004)
Get full text
Journal Article