Investigation Of Recycling And Impurities Influxes In Aditya-U Tokamak Plasmas

Fuel particle and impurity influxes have been investigated for ADITYA-U tokamak plasma operated with toroidal belt limiter using PMT based spectroscopic diagnostic system installed on machine. The influxes of hydrogen and impurity ions are estimated using various lines of sight (LoS) terminating on the graphite limiter and stainless steel wall to understand their contributions in recycled particle and impurities into the main plasma. It is found that the influxes of neutral hydrogen and oxygen are around 4 times higher in case of LoS terminating on the limiter than the wall while carbon influxes from the both LoSs are comparable. The comparable integrated particle influxes from both LoSs indicate the important role of the wall in the recycling and presence of the impurities in the plasma. The particle confinement time (tau(p)) and recycling coefficient (R) are also estimated to quantify those from the estimated particle influxes. The tau(p) values vary between 8 to 25 ms when plasma electron density is in the range of 2.0 - 3.2 x 10(19) m(-3). Analysis of recycling coefficient, R suggests that the Plasma Facing Component (PFC) acts as the particle sink at the beginning of the plasma operational campaign. The R values tend to become more than one as the campaign progresses suggesting that the PFC acting as the particle source. (C) 2021 The Japan Society of Plasma Science and Nuclear Fusion Research