Modelling of plasma performance on COMPASS-D tokamak in the presence of NBI and LHCD

Le résumé fourni par la source

The potential scenario with Neutral Beam Injection (NBI) and Lower Hybrid Current Drive (LHCD) on the COMPASS-D tokamak (R0 = 0.56 m, a = 0.17 m, m = 1.7, f = 0.4) is investigated numerically using the ASTRA and ACCOME codes. With ASTRA, the thermal electron transport in ELMy H-mode plasmas achieved previously with ohmic (OH) and electron cyclotron (EC) heating on COMPASS-D tokamak [1] is analysed with a goal of testing transport models. It is found that both the Multi-Mode Model (MMM) and mixed Bohm-gyroBohm (BgB) models [2] have to be re-normalised to achieve a satisfactory agreement with measured central electron temperature and diamagnetic energy. The re-normalisation multiplier in the MMM model has to vary from 2 (OH H-mode) to 5.8 (EC heated H-mode) while a fixed re-normalisation multiplier (equal to 7.2) has to be used in the Bohm-like term of the BgB model in order to provide a better agreement with the data. NBI heating and current drive (two 40 keV deuterium beams in co- or counter-directions with the total power of about 0.6 MW) is simulated using ACCOME and NBEAM. The possibility of obtaining a reversed shear configuration with co-injection and off-axis incidence is demonstrated. The LHCD scenario (PLH=0.4 MW, N/ / = 2.1, fLH = 1.3 GHz) for Phase I operation (Bt=1.2 T, Ipl=0.2 MA) is examined using the re-normalised BgB model with fixed re-normalisation coefficient. Device and simulation codes The COMPASS-D tokamak (R0=0.56 m, a=0.17 m, BT =1.2 T, Ip=200 kA, m=1.7, f=0.4) will be

Ce résumé expose les affirmations des auteurs. BNTIC ne l’interprète pas comme une validation indépendante des résultats.