27th IEEE Symposium on Fusion Engineering

Session

R.OP2: PMI and Plasma Edge Physics

R.OP2

8 Jun 2017, 12:40

Marriott Shanghai City Center

520. Overview of plasma surface interactions in tungsten with helium plasma exposure

Prof. Brian Wirth (University of Tennessee, Knoxville)

08/06/2017, 12:40

Plasma-material interactions, plasma edge physics

Invited Oral

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...

124. Understanding tungsten divertor sourcing, transport and its impact on core impurity accumulation in DIII-D high performance discharges

Tyler Abrams (General Atomics)

08/06/2017, 13:20

Plasma-material interactions, plasma edge physics

Invited Oral

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...

477. Utilization of isotopically enriched tungsten tracer particles and outer-midplane collector probes for impurity transport studies in the far scrape-off layer of DIII-D*,

Dr D. Donovan (University of Tennessee Knoxville)

08/06/2017, 13:40

Plasma-material interactions, plasma edge physics

Oral

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...

483. Study of D retention and impurity emission properties of oxidized B4C coatings under deuterium irradiation in NSTX-U

Felipe Bedoya (University of Illinois)

08/06/2017, 14:00

Plasma facing components

Oral

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...

203. DESIGN, CONSTRUCTION AND INSTALLATION OF LIMITER & DIVERTOR OF ADITYA-U TOKAMAK

Mr Kaushal Patel (Institute for Plasma Research)

08/06/2017, 14:20

Divertors and high heat flux components

Oral

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...