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Fusion Science and Technology Volume 68, 2015 - Issue 2: Proceedings of the Twenty-First Topical Meeting on the Technology of Fusion Energy (TOFE-2014) (Part 1) Anaheim, California, November 10–13, 2014
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Technical Paper

First Operation of the Flinak/LiPb Twin Loop Orosh2i-2 with a 3T SC Magnet for R&D of Liquid Blanket for Fusion Reactor

Akio SagaraNational Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Gifu, 509-5292, Japan
,
Teruya TanakaNational Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Gifu, 509-5292, Japan
,
Juro YagiNational Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Gifu, 509-5292, Japan
,
Mitsutoshi TakahashiSukegawa Electric. Co., Ltd., 3333-23 Kamitezuna, Takahagi, Ibaraki, 318-0004, Japan
,
Kuniaki MiuraSukegawa Electric. Co., Ltd., 3333-23 Kamitezuna, Takahagi, Ibaraki, 318-0004, Japan
,
Takehiko YokomineKyoto Univ., Kyoto daigaku-Katsura, Nishikyo, Kyoto, 615-8540, Japan
,
Satoshi FukadaKyushyu Univ., 6-1 Kasuga-Koen, Kasuga, 816-8580, Japan
&
Shintaro IshiyamaOkayama Univ., 1-1-1 Tsushima-naka, Kita-ku, Okayama, 700-8530, Japan
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Pages 303-307 | Published online: 20 Mar 2017

Citations (23)

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Shintaro Ishiyama, Teruya Tanaka, Akio Sagara & Hirotaka Chikaraishi. (2019) Demonstration Plan of Nuclear Fusion Power Generation Principle by Supercritical CO2 Gas Turbine in Oroshhi-2. Fusion Science and Technology 75:8, pages 862-872.
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Teruya Tanaka, Akio Sagara, Juro Yagi & Takeo Muroga. (2019) Liquid Blanket Collaboration Platform Oroshhi-2 at NIFS with FLiNaK/LiPb Twin Loops. Fusion Science and Technology 75:8, pages 1002-1009.
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T. Muroga, S. Fukada & T. Hayashi. (2019) Overview of Fusion Engineering Research in Japan Focusing on Activities in NIFS and Universities. Fusion Science and Technology 75:7, pages 559-574.
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Yoshinobu Yamamoto, Naoki Osawa & Tomoaki Kunugi. (2017) A New RANS Model in Turbulent Channel Flow Imposed Wall-Normal Magnetic Field with Heat Transfer. Fusion Science and Technology 72:4, pages 601-608.
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Yoshitaka Ueki, Yuya Noguchi, Juro Yagi, Teruya Tanaka, Takehiko Yokomine, Masaru Hirabayashi, Kuniaki Ara, Tomoaki Kunugi & Akio Sagara. (2017) Ultrasonic Doppler Velocimetry Experiment of Lead-Lithium Flow with Oroshhi-2 Loop. Fusion Science and Technology 72:3, pages 530-536.
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Articles from other publishers (18)

Shintaro ISHIYAMA, Akio SAGARA, Hirotaka CHIKARAISHI & Nagato YANAGI. (2022) Design Concept of Supercritical CO<sub>2 </sub>Gas Cooled Divertors in FFHR Series Fusion Reactors. Plasma and Fusion Research 17:0, pages 1405103-1405103.
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Sintaro ISHIYAMA, Akio SAGARA, Hirotaka CHIKARAISHI & Nagato YANAGI. (2022) Up-Grade Bypass Controlled Supercritical CO<sub>2 </sub>Gas Turbine for 0.6 GW<sub>th </sub>FFHR Series Fusion Reactors. Plasma and Fusion Research 17:0, pages 2405054-2405054.
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Kaito Kubo, Kazunari Katayama, Makoto Oya, Katsuya Tsukahara, Satoshi Fukada, Teruya Tanaka, Akio Sagara, Juro Yagi & Yuto Iinuma. (2021) Tritium release behavior from neutron-irradiated FLiNaBe mixed with titanium powder. Fusion Engineering and Design 171, pages 112558.
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S. Ishiyama, H. Chikaraishi & A. Sagara. (2021) Operating scenario of 3GWth class FFHR power plant with bypass controlled supercritical CO2 gas turbine power generation system. Fusion Engineering and Design 164, pages 112194.
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Oleg Zikanov, Ivan Belyaev, Yaroslav Listratov, Peter Frick, Nikita Razuvanov & Valentin Sviridov. (2021) Mixed Convection in Pipe and Duct Flows With Strong Magnetic Fields. Applied Mechanics Reviews 73:1.
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Akifumi Iwamoto & Ryosuke Kodama. (2020) Conceptual design of a subcritical research reactor for inertial fusion energy with the J-EPoCH facility. High Energy Density Physics 36, pages 100842.
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Masatoshi Kondo, Teruya Tanaka, Satoshi Fukada & Tsisar Valentyn. 2020. Comprehensive Nuclear Materials. Comprehensive Nuclear Materials 176 202 .
Fumito Okino, Juro Yagi, Teruya Tanaka, Akio Sagara & Satoshi Konishi. (2019) Current status of the continuous tritium recovery test campaign using PbLi droplets in vacuum. Fusion Engineering and Design 146, pages 898-901.
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Nagato Yanagi, Takuya Goto, Junichi Miyazawa, Hitoshi Tamura, Yoshiro Terazaki, Satoshi Ito, Teruya Tanaka, Hidetoshi Hashizume & Akio Sagara. (2018) Progress in the Conceptual Design of the Helical Fusion Reactor FFHR-d1. Journal of Fusion Energy 38:1, pages 147-161.
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Kohki Kumagai, Teruya Tanaka, Juro Yagi, Takashi Watanabe, Fuminobu Sato, Shingo Tamaki, Isao Murata & Akio Sagara. (2018) Tritium release from molten salt FLiNaK under low flux neutron irradiation with an AmBe neutron source. Fusion Engineering and Design 136, pages 1269-1272.
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Takanori Murase, Junichi Miyazawa, Teruya Tanaka, Hitoshi Tamura, Takuya Goto, Nagato Yanagi, Ryuichi Sakamoto & Akio Sagara. (2018) Thermal and flow analyses on the cartridge-type blanket CARDISTRY-B for the helical fusion reactor FFHR-c1. Fusion Engineering and Design 136, pages 106-110.
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Shoki Nakamura, Tomoaki Kunugi, Takehiko Yokomine, Zensaku Kawara, Koji Kusumi, Akio Sagara, Juro Yagi & Teruya Tanaka. (2018) MHD pressure drop measurement of PbLi flow in double-bended pipe. Fusion Engineering and Design 136, pages 17-23.
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Abhishek Saraswat, Shrikant Verma, Sandeep Gupta, A. Sarada Sree & E. Rajendra Kumar. (2018) Data-acquisition, control & interlock system design for corrosion experiments of IN-RAFM steel with flowing Pb-Li in presence of magnetic field. Fusion Engineering and Design 132, pages 119-126.
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Y. Takeiri. (2018) Prospect Toward Steady-State Helical Fusion Reactor Based on Progress of LHD Project Entering the Deuterium Experiment Phase. IEEE Transactions on Plasma Science 46:5, pages 1141-1148.
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Teruya Tanaka, Takumi Chikada, Yoshimitsu Hishinuma, Takeo Muroga & Akio Sagara. (2017) Formation of Cr 2 O 3 layers on coolant duct materials for suppression of hydrogen permeation. Fusion Engineering and Design 124, pages 1046-1051.
Crossref
A. Sagara, J. Miyazawa, H. Tamura, T. Tanaka, T. Goto, N. Yanagi, R. Sakamoto, S. Masuzaki & H. Ohtani. (2017) Two conceptual designs of helical fusion reactor FFHR-d1A based on ITER technologies and challenging ideas. Nuclear Fusion 57:8, pages 086046.
Crossref
. 2017. Molten Salt Reactors and Thorium Energy. Molten Salt Reactors and Thorium Energy 635 774 .
Yoshitaka UEKI. (2016) UVP Measurement of Lead-Lithium Flow and Nuclear Fusion Engineering Research. Journal of the Visualization Society of Japan 36:142, pages 16-20.
Crossref

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