Impact of material-dependent energy reflection coefficient on divertor heat flux in the Large Helical Device
A divertor module comprising actively-cooled tungsten (W) and carbon (C) materials placed side-by-side was simultaneously exposed to the divertor plasma in the Large Helical Device (LHD) to experimentally observe the difference in energy reflection coefficients, R iE . The divertor temperatures were measured using infrared (IR) thermography and embedded thermocouples (TCs) and were converted into heat fluxes using the finite element method (FEM). The emissivity of the W surface was evaluated using a calibration chamber. This study demonstrated that combining TC measurements and IR thermography with FEM analysis enabled accurate evaluation of the heat flux on the W even in low-temperature regions, where IR thermography is susceptible to reflection-induced overestimation. The experiment showed that the peak heat flux on the C surface reached approximately 10 MWm − 2 , while that on the W surface was ∼ 75% of this value. Furthermore, the theoretical heat fluxes were estimated using plasma parameters obtained from Langmuir probes, combined with R iE from an empirical formula. The observed ratio of heat fluxes between W and C was in good agreement with theoretical predictions based on material-dependent R iE . These results quantitatively demonstrate that the higher R iE of W can effectively reduce the absorbed heat flux by 20 to 30% compared to that with C. This finding offers important insights for the selection of plasma-facing materials and the optimization of cooling system designs. • In LHD, actively cooled W and C divertors were simultaneously exposed to divertor plasma. • IR thermography and FEM show W absorbs ∼ 75% of heat load on C, matching sheath theory. • Higher R iE of W cuts absorbed heat by 20–30%, guiding future divertor material selection.
Authors
- Shin Kajita (ORCID: https://orcid.org/0000-0003-0543-5241)
- S. Masuzaki
- M. Kobayashi (ORCID: https://orcid.org/0000-0002-0990-7093)
- Y. Hamaji (ORCID: https://orcid.org/0000-0002-9230-2334)
- Y. Hayashi (ORCID: https://orcid.org/0000-0001-6090-5010)
- K. Mukai
- M. Tokitani (ORCID: https://orcid.org/0000-0002-3744-2481)
- Takanori Murase
- Sho Nakagawa
Institutions
- National Institutes of Natural Sciences (JP)
- The Graduate University for Advanced Studies, SOKENDAI (JP)
- National Institute for Fusion Science (JP)
- The University of Tokyo (JP)
Publication Details
- Journal
- Fusion Engineering and Design
- Published
- 2025-11-06
- DOI
- https://doi.org/10.1016/j.fusengdes.2025.115509
- Primary Topic
- Fusion materials and technologies
- Type
- article
- Field-Weighted Citation Impact
- 0.00