Published October 16, 2018 | Version v1
Report

Demonstration of Power Exhaust Control by Impurity Seeding in the Island Divertor at Wendelstein 7-X

  • 1. University of Wisconsin-Madison, Madison, WI 53706 (United States)
  • 2. Institute of Energy and Climate Research, Forschungszentrum Jülich, Jülich (Germany)
  • 3. Max-Planck-Institut für Plasmaphysik, Greifswald (Germany)

Description

Full text: Effective power exhaust by impurity seeding and its dependence on the gas species used was demonstrated in island divertor configurations for the first time at Wendelstein 7- X (W7-X). A systematic set of experiments has been conducted during the first island divertor campaign which show that switching from Neon (Ne) to nitrogen (N2) as seeding gases enables switching from global to more localized edge cooling. In case of ne seeding significant enhancement of edge radiation with slow decay after end of the injection is observed due to the high recycling properties of this noble gas. The N2 seeded discharges show immediate response of local plasma parameters at the divertor target correlated to the puff duration. Fast Te recovery and drop of Prad after end of the puff suggest a rather low recycling coefficient for this impurity species. These effects are analyzed by 3D modelling with EMC3-EIRENE for high and low recycling coefficients. The impact of the 3D edge magnetic structure on radiation is investigated experimentally by changing island size and connection lengths with the island control coils in the 5/5 configuration for scenarios with ne ∼ 1.8 x 1019/m3 at PECRH ∼ 2.9 MW. A 22 ms ne puff causes enhancement of Prad by ∼ 1.6 MW. Application of full control coil currents, Icc = 2.5 kA, yields a reduction of intrinsic Prad level from ∼ 0.7 MW to 0.3 MW and an reduced increase of Prad by 1.1 MW in response to ne seeding. The change of island geometry results in a faster decay of total impurity radiation measured by an effective time constant τPrad. The presented findings on power exhaust control by impurity seeding in the W7-X island divertor are the basis for implementing radiative cooling as means to protect plasma facing components as performance levels at this new HELIAS stellarator are rising. With increasing performance, equilibrium effects will impact the 3D magnetic structure, which is addressed by equilibrium reconstruction with V3FIT and the 3D MHD code HINT. Investigating the link between the magnetic structure, the appropriate gas species, the injection location and the impurity transport is of critical importance for the goal of HELIAS divertor optimization. The experimental and numerical studies presented here represent a first-time consistent exploration of this field in the new island divertor configuration. (author)

Part of:
27th IAEA Fusion Energy Conference. Programme and Book of Abstracts

Additional details

Publishing Information

Imprint Title
27th IAEA Fusion Energy Conference. Programme and Book of Abstracts
Imprint Pagination
844 p.
Journal Page Range
p. 191
Report number
IAEA-CN--258

Conference

Title
27. IAEA Fusion Energy Conference
Acronym
FEC 2018
Dates
22-27 Oct 2018
Place
Ahmedabad (India)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
50050373
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTROL; DIVERTORS; FIRST WALL; MAGNETOHYDRODYNAMICS; NEON; NITROGEN; NUMERICAL ANALYSIS; PLASMA IMPURITIES; RADIATIVE COOLING
Descriptors DEC
COOLING; ELEMENTS; FLUID MECHANICS; FLUIDS; GASES; HYDRODYNAMICS; IMPURITIES; MATHEMATICS; MECHANICS; NONMETALS; RARE GASES; THERMONUCLEAR REACTOR WALLS

Optional Information

Collaborations
W7-X Team
Secondary number(s)
IAEA-CN--258-296