Published January 1, 2020 | Version v1
Journal article

Investigation of remaining tritium in the LHD vacuum vessel after the first deuterium experimental campaign

  • 1. National Institute for Fusion Science, National Institutes of Natural Sciences, Toki 509-5292 (Japan)
  • 2. Kindai University, Osaka 577-8502 (Japan)
  • 3. Shizuoka University, Shizuoka 422-8529 (Japan)
  • 4. Kyushu University, Kasuga 816-8580 (Japan)
  • 5. Hokkaido University, Sapporo 060-0808 (Japan)

Description

Remaining tritium in the vacuum vessel after the first deuterium plasma experimental campaign conducted over four months was investigated in the large helical device (LHD) for the first time in stellarator/heliotron devices by using the tritium imaging plate technique. In-vessel components such as divertor tiles and first wall panels, and long-term material probes retrieved from the vacuum vessel were analyzed. The in-vessel component in which tritium remained most densely is the baffle part of divertor tiles made of graphite retrieved from the inboard-side divertor. Asymmetric tritium retention is observed on divertor tiles located at magnetically symmetric positions, and can be attributed to the toroidal field direction dependence of the asymmetric loss of energetic tritons generated by deuterium–deuterium nuclear fusion reactions. On the first wall, tritium remained in a deposited layer, which mainly consists of carbon. (topical issue article)

Availability note (English)

Available from http://dx.doi.org/10.1088/1402-4896/ab6d44

Additional details

Identifiers

Publishing Information

Journal Title
Physica Scripta (Online)
Journal Volume
2020
Journal Issue
T171
Journal Page Range
[8 p.]
ISSN
1402-4896

Optional Information

Collaborations
LHD Experiment Group