Nuclear Materials and Energy (Dec 2017)

The role of the graphite divertor tiles in helium retention on the LHD wall

  • M. Oya,
  • G. Motojima,
  • M. Tokitani,
  • H. Tanaka,
  • S. Masuzaki,
  • Y. Ueda

DOI
https://doi.org/10.1016/j.nme.2017.07.006
Journal volume & issue
Vol. 13, no. C
pp. 58 – 62

Abstract

Read online

In this study, global particle balance of helium (He) long pulse discharge with graphite divertor in the Large Helical Device (LHD) and He retention in graphite from lab-scale experiments were compared in order to determine the role of the graphite divertor in He retention on the LHD wall. Global He particle balance analysis was conducted in long-pulse discharges in LHD with only turbo molecular pump. The analysis showed that static He retention was ∼2.9 × 1022 He and the ratio of retained He (= retention over fluence) was ∼0.45%. In the lab-scale study, He retention was measured by Thermal Desorption Spectroscopy (TDS) after ion irradiation or plasma exposure. The ratio of retained He were 0.1 ∼ 0.5% in all conditions, which was well consistent with LHD results. Therefore, it may be concluded that graphite divertor tiles have an important role in He absorption in the LHD wall at the initial phase of discharges.

Keywords