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

• ASAKURA Yamato

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

• SUZUKI Naoyuki

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

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.

Journal

• Plasma and Fusion Research

  Plasma and Fusion Research 7 (0), 2405009-2405009, 2012

  The Japan Society of Plasma Science and Nuclear Fusion Research

Keywords

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

Details

• CRID: 1390282680232588544
• NII Article ID: 130002059621
• NII Book ID: AA12346675
• DOI: 10.1585/pfr.7.2405009
• ISSN: 18806821
• HANDLE: 10655/8926
• Web Site: https://nifs-repository.repo.nii.ac.jp/records/501
• Web Site: https://www.jstage.jst.go.jp/article/pfr/7/0/7_0_2405009/_pdf
• Text Lang: en
• Data Source:
  • JaLC
  • IRDB
  • Crossref
  • CiNii Articles
  • KAKEN
• Abstract License Flag: Disallowed