The study of heat flux for disruption on experimental advanced superconducting tokamak

• DOI: 10.1063/1.4948494
• Publication Date: 2016-05-03T17:15:52Z
• Authors: Zhendong Yang; Jianan Fang; Xianzu Gong; Kaifu Gan; Jiarong Luo; Hailin Zhao; Zhixue Cui; Bin Zhang; Meiwen Chen
• Keywords: 13. Climate action; 0103 physical sciences; 01 natural sciences; 7. Clean energy

Disruption of the plasma is one most dangerous instabilities in tokamak. During disruption, thermal energy lost, which causes damages to facing components. Infrared (IR) camera an effective tool detect temperature distribution on first wall, and deposited wall can be calculated from surface profile measured by IR camera. This paper concentrates characteristics heat flux onto under different disruptions, including minor disruption vertical displacement events (VDE) disruption. Several disruptions have been observed before major high density experimental advanced superconducting fluxes are mainly upper/lower divertors. The magnetic configuration prior a lower single null with radial distance between two separatrices outer midplane dRsep = −2 cm, while it changes upper (dRsep 1.4 cm) during As for VDE spatial exhibits strong toroidal nonuniformity, maximum received dome plate up 11 MW/m2.