Simulation of tungsten impurity transport by DIVIMP under different divertor magnetic configurations on HL-3

Tungsten(W)accumulation in the core,depending on W generation and transport in the edge region,is a severe issue in fusion reactors.Compared to standard divertors(SDs),snowflake divertors(SFDs)can effectively suppress the heat flux,while the impact of magnetic configurations on W core accumulation remains unclear.In this study,the kinetic code DIVIMP combined with the SOLPS-ITER code is applied to investigate the effects of divertor magnetic configurations(SD versus SFD)on W accumulation during neon injection in HL-3.It is found that the W concentration in the core of the SFD is significantly higher than that of the SD with similar total W erosion flux.The reasons for this are:(1)W impurities in the core of the SFD mainly originate from the inner divertor,which has a short leg,and the source is close to the divertor entrance and upstream separatrix.Furthermore,the W ionization source(S_(W0))is much stronger,especially near the divertor entrance.(2)The region overlap of S_(W0)and F_(W,TOT)pointing upstream promote W accumulation in the core.Moreover,the influence of W source locations at the inner target on W transport in the SFD is investigated.Tungsten impurity in the core is mainly contributed by target erosion in the common flux region(CFR)away from the strike point.This is attributed to the fact that the W source at this location enhances the ionization source above the W ion stagnation point,which sequentially increases W penetration.Therefore,the suppression of far SOL inner target erosion can effectively prevent W impurities from accumulating in the core.

Simulation of charge-exchange induced NBI losses on EAST

The neutral beam injection is widely adopted in tokamaks as a key heating tool,playing a crucial role in generating burning plasmas.However,the loss of beam ions can damage the first wall and reduce the heating efficiency,resulting in failure to maintain steady-state conditions.In this work,the effect of neutral particles in the edge on fast ions generated by NBI in the Experimental Advanced Superconducting Tokamak(EAST)device is studied using the particle tracer code(PTC).The poloidal distribution of neutral particles is calculated by edge plasma simulation code SOLPS-ITER.In this simulation,four beam lines in EAST are considered:co-current tangential(co-tang),co-current perpendicular(co-perp),counter-current tangential(ctr-tang)and counter-current perpendicular(ctr-perp).It is shown that,in the absence of neutral particles,the loss fraction of ctr-injection is considerably higher than that of the co-injection.When considering the neutral particles,it is found that the ctr-perp injection demonstrates a significant variation in particles loss fraction(ranging from 18.56%to 25.42%)compared to the other three injection configurations.In terms of the loss fraction induced by neutral particles,ctr-injection exceeds co-injection,and perpendicular configuration exceeds tangential configuration.Furthermore,the difference of charge exchange ratios of three different energy(full energy,half energy,one third energy)of the four injections can be attributed to variations in the poloidal trajectories associated with each of these injections.Moreover,approximately half of fast ions which undergo neutralization directly lose to the first wall while the rest re-enter the bulk plasma and re-ionize.Except for the ctr-tang injection,the reionization ions from the other three injections exhibit effective confinement.

Plasma-tungsten interactions in experimental advanced superconducting tokamak(EAST)

Tungsten(W)is used as the armor material of the International Thermonuclear Experimental Reactor(ITER)divertor and is regarded as the potential first wall material of future fusion reactors.One of the key challenges for the successful application of W in fusion devices is effective control of W at an extremely low concentration in plasma.Understanding and control of W erosion are not only a prerequisite for W impurity control,but also vital concerns to plasma-facing component(PFC)lifetime.Since the application of ITER-like water-cooled full W divertor in EAST in 2014,great efforts were made to inves-tigate W erosion by experiment and simulation.A spectroscopic system was developed to provide a real-time measurement of W sputtering source.Both experiment and simulation results indicate that carbon(C)is the dominant impurity causing W sputtering in L-mode plasmas,which comes from the erosion of C plasma-facing material(PFM)in the lower divertor and the main chamber limiters.The mixture layer on the surface of W PFCs formed through redeposition or the wall coating can effectively suppress W erosion.Increasing the plasma density and radiation can reduce incident ion energy,thus alleviating W sputtering.In H-mode plasmas,control of edge localized mode(ELM)via resonant magnetic perturbation(RMP)proves to be capable of suppressing intra-ELM W erosion.The experiences and lessons from the EAST W divertor are beneficial to the design,manufacturing and operation of ITER and beyond.