[Table of Contents]

Plasma and Fusion Research

Volume 7, 2405023 (2012)

Regular Articles

Fuel Particle Balance Study in FFHR DEMO Reactor
Masahiro TANAKA, Takuya GOTO, Yasuji KOZAKI, Akio SAGARA and the FFHR Design Group
National Institute for Fusion Science, 322-6 Oroshi-cho, Toki 509-5292, Japan
(Received 9 December 2011 / Accepted 3 February 2012 / Published 10 May 2012)

Abstract

Tritium particle balance in the FFHR DEMO reactor is investigated with consideration of the fueling efficiency by pellet injection system, retention loss in a vacuum vessel and permeation loss from the fuel processing system. In order to satisfy the fuel balance and the tritium safety management, it was necessary to suppress the tritium retention rate to be 10−5 and the DFs in the tritium cycle systems to above 107 with the tritium breeding ratio of 1.08. The processing throughput for the tritium processing system is estimated to be about 400 mol/h, which is almost same as the throughput of the fuel stream for the ITER. Therefore, the tritium processing system for vacuum exhaust gas for the DEMO will not be necessary to improve the system for the ITER further. On the other hands, the significant development of the tritium processing system for the effluent disposal and the waste materials from the safety aspect and the social acceptance will be required toward the DEMO reactor.

Keywords

particle balance, DEMO reactor, tritium processing system, fueling efficiency, tritium retention, tritium permeation, decontamination factor, tritium safety handling

DOI: 10.1585/pfr.7.2405023

Full Text

PDF format (647Kbytes) PDF Download

References

  • [1] A. Sagara et al., to be published in Fusion Eng. Des.
  • [2] J. Roth et al., J. Nucl. Mater. 390-391, 1 (2009).
  • [3] S. Kuroki et al., J. Nucl. Sci. Technol. 19, 186 (1982).
  • [4] M. Nishikawa, Fusion Sci. Technol. 57, 120 (2010).
  • [5] H. Takenaga et al., Fusion Sci. Technol. 57, 94 (2010).
  • [6] A. Busigin et al., Fusion Technol. 21, 915 (1992).
  • [7] W. Kuan et al., Fusion Eng. Des. 28, 329 (1995).
  • [8] I. Aoki et al., Fusion Sci. Technol. 41, 835 (2002).
  • [9] I.-R. Cristescu et al., Fusion Sci. Technol. 48, 134 (2005).
  • [10] L.R. Bayor et al., Nucl. Fusion 47, 443 (2007).
  • [11] S. Masuzaki et al., J. Nucl. Mater. 290-293, 12 (2001).
  • [12] S. Masuzaki et al., Plasma Phys. Control. Fusion 44, 795 (2002).
  • [13] S. Masuzaki et al., proceedings in ITC-21 (2011).
  • [14] A. Sagara et al., Fusion Eng. Des. 83, 1690 (2008).
  • [15] S. Morita et al., Trans. Fusion Technol. 27, 239 (1995).
  • [16] S. Konishi et al., Fusion Eng. Des. 83, 954 (2008).
  • [17] C.A. Gentile et al., Fusion Sci. Technol. 48, 200 (2005).
  • [18] M. Nishi et al., Fusion Eng. Des. 81, 745 (2006).

This paper may be cited as follows:

Masahiro TANAKA, Takuya GOTO, Yasuji KOZAKI, Akio SAGARA and the FFHR Design Group, Plasma Fusion Res. 7, 2405023 (2012).