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Blanket Material and Process

Mass-Transport Properties to Estimate Rates of Tritium Recovery from Flibe Blanket

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Pages 1054-1058 | Published online: 10 Aug 2017

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Read on this site (5)

Sara E. Ferry, Kevin B. Woller, Ethan E. Peterson, Caroline Sorensen & Dennis G. Whyte. (2023) The LIBRA Experiment: Investigating Robust Tritium Accountancy in Molten FLiBe Exposed to a D-T Fusion Neutron Spectrum. Fusion Science and Technology 79:1, pages 13-35.
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T. Muroga, T. Tanaka, Zaixin Li, A. Sagara & Dai-Kai Sze. (2007) Tritium Control for Flibe/V-Alloy Blanket System. Fusion Science and Technology 52:3, pages 682-686.
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S. Fukada, K. Katayama, T. Terai & A. Sagara. (2007) Recovery of Tritium from Flibe Blanket in Fusion Reactor. Fusion Science and Technology 52:3, pages 677-681.
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Satoshi Fukada, Robert A. Anderl, Akio Sagara & Masabumi Nishikawa. (2005) Diffusion Coefficient of Tritium Through Molten Salt Flibe and Rate of Tritium Leak from Fusion Reactor System. Fusion Science and Technology 48:1, pages 666-669.
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S. Fukada, R. A. Anderl, R. J. Pawelko, G. R. Smolik, S. T. Schuetz, J. E. O’Brien, H. Nishimura, Y. Hatano, T. Terai, D. A. Petti, D.-K. Sze & S. Tanaka. (2003) Flibe-D2 Permeation Experiment and Analysis. Fusion Science and Technology 44:2, pages 410-414.
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Alexander Petrov, Tom Stroud, Daniel Blackburn, Taiwo Owoeye, Steven Wray, Kristian Zarebski, Jack Acres, Mohamad Abdallah, Chris Clements, Marius Cannon, Finlay Christie, Timothy Jackson, Vignesh Laksharam, Samuel Stewart, Rhys Griffiths, Nicholas Brewer, Katherine Rochford & Sophie Gribben. (2023) An open-source power balance model for the estimation of tokamak net electrical power output. Fusion Engineering and Design 191, pages 113563.
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Gaku Yamazaki, Takuya Nagasaka, Teruya Tanaka, Takuya Goto, Jingjie Shen, Kazuki Saito & Makoto I. Kobayashi. (2021) Corrosion of pure Cr and W in molten FLiNaK with hydrogen fluoride solution. Fusion Engineering and Design 172, pages 112741.
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Takashi Watanabe, Akio Sagara, Juro Yagi, Toru Tsujimura, Gaku Yamazaki, Kohki Kumagai & Teruya Tanaka. (2018) Hydrogen recovery from metal particle dispersed salt by selective microwave heating. Fusion Engineering and Design 136, pages 1396-1399.
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S. Fukada, Y. Edao, S. Yamaguti & T. Norimatsu. (2008) Tritium recovery system for Li–Pb loop of inertial fusion reactor. Fusion Engineering and Design 83:5-6, pages 747-751.
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S. Fukada, M.F. Simpson, R.A. Anderl, J.P. Sharpe, K. Katayama, G.R. Smolik, Y. Oya, T. Terai, K. Okuno, M. Hara, D.A. Petti, S. Tanaka, D.-K. Sze & A. Sagara. (2007) Reaction rate of beryllium with fluorine ion for Flibe redox control. Journal of Nuclear Materials 367-370, pages 1190-1196.
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Satoshi Fukada & Akio Morisaki. (2006) Hydrogen permeability through a mixed molten salt of LiF, NaF and KF (Flinak) as a heat-transfer fluid. Journal of Nuclear Materials 358:2-3, pages 235-242.
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Satoshi Fukada, Akio Morisaki, Akio Sagara & Takayuki Terai. (2006) Control of tritium in FFHR-2 self-cooled Flibe blanket. Fusion Engineering and Design 81:1-7, pages 477-483.
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Satoru TANAKA, Masato AKIBA, Mikio ENOEDA, Akira HASEGAWA, Satoshi KONISHI, Takeo MUROGA & Akio SAGARA. (2005) Present Status of ITER Test Blanket DevelopmentITERテストブランケット開発の現状. Journal of Plasma and Fusion Research 81:6, pages 434-450.
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Masabumi NISHIKAWA, Satoshi FUKADA, Akihiko SHIMIZU & Tetsuo IGUCHI. (2003) The Frontiers of Research on Fusion Blanket Technologyブランケット開発の最新動向  5.ブランケット工学の最前線. Journal of Plasma and Fusion Research 79:7, pages 678-686.
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Akio SAGARA, Mikio ENOEDA, Satoshi NISHIO & Yasuji KOZAKI. (2003) Current Trends of Blanket Research and Deveopment in Japan 3.Blanket Designs in Fusion Power Reactors. Journal of Plasma and Fusion Research 79:7, pages 663-671.
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