Plasma and Fusion Research
Volume 13, 3403034 (2018)
Regular Articles
- 1)
- National Institute for Fusion Science, National Institutes of Natural Sciences, Toki 509-5292, Japan
- 2)
- Department of Fusion Science, Graduate University for Advanced Studies (SOKENDAI), Toki 509-5292, Japan
- 3)
- Max-Planck-Institut für Plasmaphysik, D-17491 Greifswald, Germany
Abstract
Recently, a new limiter concept with liquid metal for a helical fusion reactor was proposed. This work present a modeling study to understand the influence of the limiter to the plasma and to find critical parameters for the liquid limiter concept. EMC3-EIRENE code is applied to a limiter configuration of a vertical column formed with plane surfaces at the inboard side of the Large Helical Device (LHD). The calculation results indicate that heat load on the helical divertor plates is significantly reduced when the limiter is inserted into the ergodic layer even without impurities. However, the influence of impurity radiation is too large in some cases. In order to achieve a large reduction of divertor flux and to avoid a large reduction of core electron temperature, parameter scans with limiter position and sputtering yield were performed. The results suggest that the limiter position is a critical parameter for acceptable degradation of the core and sufficient reduction of divertor flux.
Keywords
EMC3-EIRENE, modeling, liquid metal, limiter, divertor
Full Text
References
- [1] J. Miyazawa et al., Fusion Eng. Des. 125, 227 (2017).
- [2] Y. Feng et al., Contrib. Plasma Phys. 54, 426 (2014).
- [3] Y. Feng et al., Contrib. Plasma Phys. 44, 57 (2004).
- [4] D. Reiter et al., Nucl. Fusion 47, 172 (2005).
- [5] OPEN-ADAS http://open.adas.ac.uk/
- [6] G. Kawamura et al., Contrib. Plasma Phys. 54, 437 (2014).
- [7] G. Kawamura et al., “Three-dimensional impurity transport modeling of neon-seeded and nitrogen-seeded LHD plasmas” submitted to Plasma Phys. Control. Fusion.
- [8] T. Morisaki et al., Nucl. Fusion 53, 063014 (2013).
- [9] M. Kondo et al., Fusion. Eng. Des. 88, 2556 (2013).
- [10] M.D. Coventry et al., J. Nucl. Mater. 335, 115 (2004).