Abstract
The Electron Cyclotron Resonance Heating (ECRH) system of China Fusion Engineering Test Reactor (CFETR) is designed to inject 20 MW RF power into the plasma for heating and current drive (H&CD) applications. The ECRH system consists of 20 gyrotrons, the associated power supplies, the transmission lines and one launcher. In order to compare the launcher performance from equatorial and upper ports, two types of launcher are designed in this paper. In equatorial launcher (EL), twenty in-vessel transmission lines are divided into four groups. Every five gaussian beams from in-vessel transmission lines face one fixed focusing mirror and one steering mirror. All gaussian beams are injected into the plasma with optimal toroidal and poloidal angles calculated by C3PO/LUKE code. In upper launcher (UL), twenty-one transmission lines are supposed and divides into three groups. Every seven gaussian beams are injected into one fixed focusing mirrors and all twenty-one beams reflected to one common steering mirror finally. The optical transmission characteristics and the convergence information of gaussian beams are checked and optimized. The EL or UL is installed on the equatorial or upper port with a port-plug modular structure.
Highlights
The objective for International Thermonuclear Experimental Reactor (ITER) [1] is to demonstrate the scientific and technological feasibility of applying fusion energy for peaceful purposes
To assist and sustain China Fusion Engineering Test Reactor (CFETR) operation in various scenarios, basing on the design experience of EAST ECH system [4,5], an ECH&ECCD system [6,7] operating at 170 GHz, 20 MW power continuous wave (CW) will be installed for the CFETR with the power injected via two types of launchers, the equatorial launcher and the upper launcher
According to the port position of CFETR tokamak, two types of injection launcher——equatorial launcher (EL) and upper launcher (UL) are designed with quasi-optics transferring pattern
Summary
The objective for International Thermonuclear Experimental Reactor (ITER) [1] is to demonstrate the scientific and technological feasibility of applying fusion energy for peaceful purposes. The mission and goal of CFETR are as follows: (1) Fusion power 200- 1500 MW; (2) Duty cycle time (or burning time) ≧50%; (3) Tritium should be self-sufficiency by blanket, TBR (Tritium Breeding Ratio) ≧1. It is challenged by integrated design considering all crucial elements [2,3], which include integrated plasma scenarios for steady-state operation and engineering optimization, inboard radial space for tritium breeding modules and the tradeoff of plasma faced surface for tritium breeding and heating and current drive (H and CD), diagnostics, burning ratio of fuelled particles, plasma burning duty factor, RH, and so on.
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