Numerical analyses of JT-60SA tokamak with tungsten divertor by COREDIV code

• Published in: Plasma physics and controlled fusion Vol. 59; no. 4; pp. 45011 - 45021
• Main Authors: Ga zka, K, Ivanova-Stanik, I, St pniewski, W, Zagórski, R, Neu, R, Romanelli, M, Nakano, T
• Format: Journal Article
• Language: English
• Published: IOP Publishing 01.04.2017
• Subjects: COREDIV; integrated core-SOL modeling; JT-60SA; self-consistient modeling; thermonuclear fusion; tokamak
• ISSN: 0741-3335; 1361-6587
• DOI: 10.1088/1361-6587/aa5c58

An analysis of radiative power exhaust for the JT-60SA tokamak with a tungsten divertor is performed with the help of the self-consistent, core-edge integrated COREDIV code. Two scenarios of operation (low and high density) were investigated in the scope of different parameters (electron density at the separatrix and the perpendicular transport in the scrape-off layer) with impurity seeding (Ne and Kr). The calculations show that in the case of the tungsten divertor the power load to the divertor plate is mitigated and the central plasma dilution is smaller compared to the carbon divertor. In the most cases the energy flux through the separatrix is above the L-H transition threshold. For the high density case with neon seeding operation in full detachment mode is observed. Changing the diffusion coefficient in the SOL has a strong influence on the result of the calculations as increased radial transport causes stronger screening effect. Also by changing the electron density on the separatrix the influx of heavy impurities (W, Kr) into the core region can be reduced. The results demonstrate that it is easier to achieve sustainable conditions in the divertor region for the high density scenario, whereas for the low density one reducing the auxiliary heating power seems unavoidable to prevent damaging of the target plate, even for strong seeding gas influx.