Plasma density estimation of a fusion grade ICP source through electrical parameters of the RF generator circuit

摘要

An inductively coupled plasma (ICP) based negative hydrogen ion source is chosen for ITER neutral beam (NB) systems. To avoid regular maintenance in a radioactive environment with high flux of 14 MeV neutrons and gamma rays, invasive plasma diagnostics like probes are not included in the ITER NB source design. While, optical or microwave based diagnostics which are normally used in other plasma sources, are to be avoided in the case of ITER sources due to the overall system design and interface issues. In such situation, alternative forms of assessment to characterize ion source plasma become a necessity. In the present situation, the beam current through the extraction system in the ion source is the only measurement which indicates plasma condition inside the ion source. However, beam current not only depends on the plasma condition near the extraction region but also on the perveance condition and negative ion stripping. Apart from that, the ICP production region radio frequency (RF) driver region) is placed far (～30 cm) from the extraction region. Therefore, there are uncertainties involved in linking the beam current with plasma properties inside the RF driver. To maintain the optimum condition for source operation it is necessary to maintain the optimum conditions in the driver. A method of characterization of the plasma density in the driver without using any invasive or non-invasive probes could be a useful tool to achieve that objective. Such a method, which is exclusively for ICP based ion sources, is presented in this paper. In this technique, plasma density inside the RF driver is estimated through the measurements of the electrical parameters in the RF power supply circuit path. Monitoring RF driver plasma through the described route will be useful during the source commissioning phase and also in the beam operation phase.