ECRF stray radiation studies in preparation of the operations of JT-60SA

¹ Institute for Plasma Science and Technology (ISTP-CNR), Italy
² National Institutes for Quantum and Radiological Science and Technology, QST, Naka, Ibaraki 311-0193, Japan
³ CCFE, Culham Science Centre, Abingdon, UK

^* Corresponding author: carlo.sozzi@istp.cnr.it

Published online: 23 February 2023

Abstract

JT-60SA tokamak is equipped with an ECRF system since the beginning of its operational phase. Starting from two gyrotrons units during the Integrated Commissioning, applicable for core heating, assisted breakdown and assisted Wall Conditioning, the system capabilities will be progressively extended from the Initial Research phase for wider applications. The development of the full current plasma H mode scenario 2 (inductive, type I ELM, I_p=5.5 MA, B_T=2.25 T, q₉₅=3) is among the first scientific objectives of the research program. In preparation of this, predictive modelling of the current ramp-up in scaled versions of scenario 2 is being done, based on parameters previously published. In this scenario the ECRF power is injected from an early phase of the discharge. Such modelling provides the kinetic profiles giving the opportunity to estimate the expected amount of EC stray radiation during the ramp-up phase when the EC power absorption might be less than 100% and consequently the potential risk of damage of the in-vessel components is higher.