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Fusion Science and Technology Volume 48, 2005 - Issue 1: Proceedings of the Seventh International Conference on Tritium Science and Technology Baden-Baden, Germany September 12–17, 2004
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Technical Paper

Diffusion Coefficient of Tritium Through Molten Salt Flibe and Rate of Tritium Leak from Fusion Reactor System

Satoshi FukadaKyushu University, Hakozaki, Fukuoka 812-8581, Japan, [email protected], [email protected].
,
Robert A. AnderlIdaho National Engineering and Environmental Laboratory, Idaho Falls, ID 83415-7113, USA, [email protected]
,
Akio SagaraNational Institute for Fusion Science, Toki 509-5292, Japan, [email protected]
&
Masabumi NishikawaKyushu University, Hakozaki, Fukuoka 812-8581, Japan, [email protected], [email protected].
Pages 666-669 | Published online: 07 Apr 2017

Citations (15)

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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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Yuuki Edao, Satoshi Fukada, Hidetaka Noguchi, Yasushi Maeda & Kazunari Katayama. (2009) Isotope Effects of Hydrogen Isotope Absorption and Diffusion in Li0.17Pb0.83 Eutectic Alloy. Fusion Science and Technology 56:2, pages 831-835.
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Yuki Edao, Satoshi Fukada, Hidetaka Noguchi & Akio Sagara. (2009) Tritium Release from Neutron-Irradiated Flibe Purged Out by Ar-H2 or Ar at Controlled Temperature. Fusion Science and Technology 55:2, pages 140-151.
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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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Articles from other publishers (10)

Xuejiao Li, Tingrui Xu, Mengmeng Liu & Yong Zuo. (2022) Diffusion behaviors of HF in molten LiF-BeF2 and LiF-NaF-KF eutectics studied by FPMD simulations and electrochemical techniques. Journal of Nuclear Materials 572, pages 154031.
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Masatoshi Kondo, Teruya Tanaka, Satoshi Fukada & Tsisar Valentyn. 2020. Comprehensive Nuclear Materials. Comprehensive Nuclear Materials 176 202 .
Sheng Zhang, Xiao Wu, Shanbin Shi, Xiaodong Sun, Richard Christensen & Graydon Yoder. (2018) A coupled heat transfer and tritium mass transport model for a double-wall heat exchanger design for FHRs. Annals of Nuclear Energy 122, pages 328-339.
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John D. Stempien, Ronald G. Ballinger & Charles W. Forsberg. (2016) An integrated model of tritium transport and corrosion in Fluoride Salt-Cooled High-Temperature Reactors (FHRs) – Part I: Theory and benchmarking. Nuclear Engineering and Design 310, pages 258-272.
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Shuichi Yamada, Akio Sagara, Shinsaku Imagawa & Osamu Motojima. (2009) Study on hydrogen production from steam electrolysis in LHD-type power reactor FFHR. Fusion Engineering and Design 84:7-11, pages 1997-2001.
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P. Calderoni, P. Sharpe, M. Hara & Y. Oya. (2008) Measurement of tritium permeation in flibe (2LiF–BeF2). Fusion Engineering and Design 83:7-9, pages 1331-1334.
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S. Yamada, A. Sagara, S. Imagawa, T. Mito & O. Motojima. (2007) Conceptual design of the cryogenic system for the helical-type fusion power plant FFHR. Fusion Engineering and Design 82:15-24, pages 2817-2823.
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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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