The performance of plasma facing components (PFC) is one of the main issues facing ITER and future magnetic fusion reactors. Tungsten will be used in ITER as the PFC material and is considered to be one of the primary candidates for future reactors. However, recent experiments that exposed tungsten to He plasma exposure or He ion irradiation with ion energy less than about 100 eV (well below...
Using two toroidal rings of isotopically enriched tungsten-coated metal inserts in the predominantly carbon DIII-D divertor, detailed information on W sourcing, transport, and core contamination has been acquired over a range of high performance plasma conditions. W is the planned plasma facing material for the ITER divertor, but its contamination of the core plasma can have deleterious...
First-of-its-kind experiments using isotopically-enriched, W-coated divertor tiles coupled with midplane collector probes (CPs) have been performed on DIII-D to understand divertor impurity production and transport. Inductively Coupled Plasma Mass Spectroscopy (ICP-MS) results are presented characterizing the isotopic ratios of deposited W on the mid-plane CPs and give quantitative information...
Conditioning and irradiation induced modifications on Plasma Facing Component (PFC) materials play a key role in the plasma performance in tokamak machines. Boronization is a conditioning technique widely used in carbon based machines due to its associated sputtering reduction and oxygen gettering properties. The National Spherical Tokamak Upgrade (NSTX-U) used boronization with d-TMB during...
The ADITYA tokamak (R0 = 75 cm, a = 25 cm)[1] having a limiter configuration has been upgraded to a state-of-art ADITYA-U tokamak[2] with divertor configuration to support the future Indian Fusion program. Limiter and Divertor are the most important subsystems of any tokamak. They are used to form the plasma boundary inside the tokamak and restrict the high-temperature plasma from hitting the...
