Comparative Divertor-Transport Study for Helical Devices

نویسنده

  • Y. Feng
چکیده

Using the island divertors (ID) of W7-AS and W7-X and the helical divertor (HD) of LHD as examples, the paper presents a comparative divertor transport study for three typical helical devices of different machine-size following two distinct divertor concepts, aiming at identifying common physics issues/effects for mutual validation and combined studies. Based on EMC3/EIRENE simulations supported by experimental results, the paper first reviews and compares the essential transport features of the W7-AS ID and the LHD HD in order to build a base and framework for a predictive study of W7-X. Revealed is the fundamental role of the low-order magnetic islands in both divertor concepts. Preliminary EMC3/EIRENE simulation results for W7-X are presented and discussed with respect to W7-AS and LHD in order to show how the individual field and divertor topologies affect the divertor transport and performance. For instance, a high recycling regime which is absent from W7-AS and LHD is expected for W7-X. Topics addressed are restricted to the basic function elements of a divertor such as particle flux enhancement and impurity retention. In particular, the divertor function on reducing the influx of intrinsic impurities is examined for all the three devices under different divertor plasma conditions. Special attention is paid to examining the island screening potential of intrinsic impurities which has been predicted for all the three devices under high divertor collisionality conditions. The results are discussed in conjunction with the experimental observations for high density divertor plasmas in W7-AS and LHD.

برای دانلود رایگان متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

منابع مشابه

EX/P4-24 Advanced Divertor Scenario in the Large Helical Device

Neutral particle behavior in the Large Helical Device heliotron has been investigated to conduct the effective particle control using the intrinsic helical divertor. The torus in–out asymmetry was observed in the neutral pressure distribution, and the degree of the asymmetry depends on the divertor particle flux distribution, and thus, on the operational magnetic configuration. This asymmetry w...

متن کامل

Neutral Particle Dynamics in the Alcator

This thesis presents an experimental study of neutral particle dynamics in Alcator C-Mod a high powerand particle-density tokamak with an advanced poloidal divertor. The primary diagnostic used in the study is a set of six neutral pressure gauges, including special-purpose gauges built for in situ tokamak operation. While a low main chamber neutral pressure coincides with high plasma confinemen...

متن کامل

Damage to nearby divertor components of ITER-like devices during giant ELMs and disruptions

During normal operation of the high confinement mode in future ITER devices, edge-localized modes (ELMs) are a potential threat to the divertor components lifetime and plasma contamination. To predict the outcome of the direct ELM plasma impact on the divertor plate, conversion of plasma energy into radiation in the shielding layer, and then the resulting energy deposition of radiation flux to ...

متن کامل

Wave Motion and Stop-Bands in Pipes with Helical Characteristics Using Wave Finite Element Analysis

Pipes are widely used in many industrial and mechanical applications and devices. Although there are many different constructions according to the specific application and device, these can show helical pattern, such as spiral pipes, wire-reinforced pipes/shells, spring-suspension, and so on. Theoretical modelling of wave propagation provides a prediction about the dynamic behavior, and it is f...

متن کامل

Analysis of tungsten migration from the C-MOD divertor; prediction of high redeposition rate, and code validation progress

For acceptable magnetic fusion reactor performance it is critical that net erosion of high-Z plasma facing material be much less than gross erosion. A detailed simulation of outer divertor-sputtered tungsten migration in the C-MOD tokamak, over an extended plasma campaign, shows a high ratio, ∼×10, of gross/net erosion, no core plasma contamination, and moderate transport of tungsten to lower d...

متن کامل

ذخیره در منابع من


  با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید

عنوان ژورنال:

دوره   شماره 

صفحات  -

تاریخ انتشار 2008