The use of the Electron Cyclotron Resonance Heating and Current Drive (ECRH&CD) system is considered essential for granting reliable plasma operation in future fusion reactors. In this work we present the quantitative study of the performances of the EC system in the main scenario foreseen for the first planned reactor DEMO (DEMO1 [1]), focusing on the following topics: (i) optimization of the CD efficiency and of the localization of the power and current deposition for the physics tasks regarding bulk heating (BH), CD and Neoclassical Tearing Modes (NTM) mitigation in the flat top phase; and (ii) first evaluations about the feasibility of the injection and absorption of significant amount of EC power in the plasma density pedestal region for Thermal Instability (TI) control. To accomplish these tasks, the EC system must provide proper different radial localizations and combination of heating and non-inductive CD, taking into account the peculiar physics requirements and the engineering constraints of a fusion power plant reactor. In order to find suitable launcher configurations, the beam tracing code GRAY [2] has been used to perform scans in the launcher parametric space defined by the injection angles, the wave frequency and the antenna position.
ECRH and ECCD modeling studies for DEMO scenarios
Baiocchi B;Bruschi A;Figini L;Garavaglia S;Granucci G;Moro A
2021
Abstract
The use of the Electron Cyclotron Resonance Heating and Current Drive (ECRH&CD) system is considered essential for granting reliable plasma operation in future fusion reactors. In this work we present the quantitative study of the performances of the EC system in the main scenario foreseen for the first planned reactor DEMO (DEMO1 [1]), focusing on the following topics: (i) optimization of the CD efficiency and of the localization of the power and current deposition for the physics tasks regarding bulk heating (BH), CD and Neoclassical Tearing Modes (NTM) mitigation in the flat top phase; and (ii) first evaluations about the feasibility of the injection and absorption of significant amount of EC power in the plasma density pedestal region for Thermal Instability (TI) control. To accomplish these tasks, the EC system must provide proper different radial localizations and combination of heating and non-inductive CD, taking into account the peculiar physics requirements and the engineering constraints of a fusion power plant reactor. In order to find suitable launcher configurations, the beam tracing code GRAY [2] has been used to perform scans in the launcher parametric space defined by the injection angles, the wave frequency and the antenna position.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
