[Table of Contents]

Plasma and Fusion Research

Volume 7, 2405080 (2012)

Regular Articles

Hydrogen Recovery from Liquid Li with Y Hot Trap
Satoshi SHIGEHARU, Yusuke HATACHI, Tetsushi HIROMOTO, Yuki EDAO and Satoshi FUKADA
Department of Advanced Energy Engineering Science, Kyushu University, 6-10-1 Hakozaki, Higashi-ku, Fukuoka 812-8581, Japan
(Received 9 December 2011 / Accepted 29 March 2012 / Published 26 July 2012)


Materials to compose a fusion reactor chamber are subjected to neutron irradiation. International Fusion Materials Irradiated Facility (IFMIF) will be used to analyze how neutron damage affects material durability. The material is irradiated by high-intensity neutron beam, which is generated by the D-Li stripping reaction. Tritium (T) generated by by-pass reaction needs to be recovered from liquid Li for safety. Recovery of tritium by an yttrium (Y) hot trap is one of the ways to recover T from liquid Li in IFMIF. Therefore, it is necessary to analyze the behavior of T in the liquid Li. In this study, the authors measured H2 absorption rates under stirred conditions of liquid Li and analyzed the effect of hydrogen absorption rate of Y by elevating temperature from 250°C to 400°C to establish the way to recover T from liquid Li with the Y hot trap in IFMIF. Judging from the comparison, we considered the rate-determining step is H diffusion in Y. Mass transfer coefficients at each temperature were determined by fitting the results between calculation and experiment.


hydrogen isotope, liquid lithium, recovery, rotating rate, H concentration, mass transfer coefficient

DOI: 10.1585/pfr.7.2405080


  • [1] H. Nakamura et al., Fusion Eng. Des. 83, 1007 (2008).
  • [2] H. Nakamura et al., J. Nucl. Mater. 329, 202 (2004).
  • [3] K. Katekari, Y. Hatachi, Y. Edaoand and S. Fukada, “Hydrogen Isotopes Recovery from Liquid Lithium under Dynamic Conditions,” Journal of Energy and Power Engineering, Volume 4, No. 1 (Serial No. 26) Jan. 2011.
  • [4] K. Nakamura et al., “Present status of Japanese tasks for lithium target facility under IFMIF/EVEDA”, Fusion Eng. Des., in printing.
  • [5] R.E. Buxbaum and E.F. Johnson, Ind. Eng. Chem. Fundam. 24, 180 (1985).
  • [6] S. Fukada, Y. Maeda, M. Kinoshita and T. Muroga, Fusion Eng. Des. 82, Issues 15-24, 2152 (2007).
  • [7] Y. Wu, Y. Edao, S. Fukada, H. Nakamura and H. Kondo, Fusion Eng. Des. 85, 1484 (2010).

This paper may be cited as follows:

Satoshi SHIGEHARU, Yusuke HATACHI, Tetsushi HIROMOTO, Yuki EDAO and Satoshi FUKADA, Plasma Fusion Res. 7, 2405080 (2012).