Experiment of Recovery of Tritium from Li by Y and Design of Hot Trap-Reference-Cited by-同舟云学术

Experiment of Recovery of Tritium from Li by Y and Design of Hot Trap

Published:2008-07 Issue:1 Volume:54 Page:117-121
ISSN:1536-1055
Container-title:Fusion Science and Technology
language:en
Short-container-title:Fusion Science and Technology

Author:

Fukada Satoshi¹,Maeda Yasushi¹,Edao Yuuki¹

Affiliation:

1. Department of Advanced Energy Engineering Science, Kyushu University: 6-10-1 Hakozaki, Higashi-ku, Fukuoka 812-8581, Japan, E-mail sfukada@nucl.kyushu-u.ac.jp

Publisher

Informa UK Limited

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Civil and Structural Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/FST08-A1777

Reference15 articles.

1. Removal and Control of Tritium in Lithium Target for International Fusion Materials Irradiation Facility (IFMIF)

2. Hydrogen and Oxygen Behavior in Liquid Sodium (Experimental)

3. Decomposition pressures in the (α + β) fields of the Li-LiH, Li-LiD, and Li-LiT systems

4. The Use of Yttrium for the Recovery of Tritium from Lithium at Low Concentrations

5. The solubility of tritium in yttrium at temperatures from 250 to 400 °c

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1. Trapping of deuterium dissolved in fluidized Li by Y;Fusion Engineering and Design;2014-10

2. Chemical Analysis of Hydrogen Isotopes Dissolved in Li and Y for Hot Trap of IFMIF Target Loop;Fusion Science and Technology;2013-09

3. Tritium Recovery from Liquid Blanket Systems for Fusion Reactor;Fusion Science and Technology;2012-01

4. Design and Construction of IFMIF/EVEDA Lithium Test Loop;Journal of Engineering for Gas Turbines and Power;2010-12-16

5. Removal rates of hydrogen isotope from liquid Li by HF-treated Y plate;Fusion Engineering and Design;2010-12