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Planned Operation of Tritium Recovery System Based on Investigation of LHD Exhaust System

Yamato ASAKURA and Naoyuki SUZUKI

National Institute for Fusion Science, 322-6 Oroshi-cho, Toki 509-5292, Japan

(Received 25 November 2011 / Accepted 23 January 2012 / Published 17 February 2012)

Abstract

To understand the conditions of exhaust gas treatment at the transition point between the Large Helical Device (LHD) vacuum pumping system and the exhaust gas tritium recovery system, the gas flow rate and hydrogen concentration were measured. Simultaneous measurement of the exhaust gas flow rate and hydrogen concentration was made possible by applying two types of hydrogen monitors: a thermal conductivity sensor and a combustible gas sensor. The obtained results have led to remodeling of the LHD vacuum pumping system and an optimised plan of operation for the tritium recovery system.

Copyright (c) 2012 The Japan Society of Plasma Science and Nuclear Fusion Research

Keywords

tritium, hydrogen monitor, tritium recovery, vacuum pumping, exhaust gas, large helical device

DOI: 10.1585/pfr.7.2405009

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References

• [1] T. Uda et al., Fusion Sci. Technol. 41, 652 (2002).
• [2] Y. Asakura et al., J. Nucl. Sci. Technol. 41, 863 (2004).
• [3] Y. Asakura et al., J. Nucl. Sci. Technol. 46, 641 (2009).
• [4] Y. Asakura et al., Fusion Sci. Technol. 60, 1363 (2011).

This paper may be cited as follows:

Yamato ASAKURA and Naoyuki SUZUKI, Plasma Fusion Res. 7, 2405009 (2012).