Published May 3, 2018 | Version v1
Report

The Role of the Density Profile Location on Pedestal Stability in ASDEX-Upgrade

  • 1. Max-Planck-Institut fuer Plasmaphysik, Garching (Germany)
  • 2. KTH Royal Institute of Technology, Stockholm (Sweden)
  • 3. Forschungszentrum Juelich, Juelich (Germany)
  • 4. Culham Centre for Fusion Energy (CCFE), Culham Science Centre, Abingdon (United Kingdom)
  • 5. Institute for Applied Physics, Technische Universitaet Wien, 1040 Vienna (Austria)

Description

Full text: Scrape-off layer (SOL) properties are controlled by a number of parameters, such as heating power, main ion fuelling, and impurity seeding. The high field side high density (HFSHD) is a region of high density (∼10 higher than the separatrix density) localized to the HFS SOL and is observed in both ASDEX-Upgrade (AUG) and JET when a gas puff at sufficient heating power is applied. It can be mitigated by either reducing the input power to the main plasma or by radiating this power, via, for example, nitrogen seeding, before it reaches the HFS SOL. Observations of the density profile and the HFSHD show that the presence of the HFSHD is linked with an outward shift of the density profile. Conversely, when it is mitigated, the profile shifts radially inwards. At the same time, nitrogen seeding has been observed to increase pedestal and global confinement in fuelled discharges on AUG by up to 40%. Interpretive pedestal modelling is used to validate the peeling-ballooning hypothesis of pedestal limiting ELM behaviour. While this is a valuable tool, it is limited since only final plasma states involving a variety of changes in impurity content, SOL characteristics, and global β can be analyzed. As such, a predictive pedestal tool (iPED) was developed using similar assumptions to the EPED model to vary each parameter independently. In addition to the standard inputs of predictive pedestal models, an ad-hoc shift of the density profile, based on experimental measurements, is included. An inward shift (of up to 0.01 ρpoloidal) has a dramatic impact on the predicted pedestal stability, increasing it by ∼30% in a typical AUG scenario and is the dominant factor determining the eventual pedestal top. Increased Zeff and global β also contribute to pedestal stabilization, but have a smaller impact. To determine the final global plasma state, iPED is combined with the ASTRA transport model. ASTRA and iPED are iterated in a step-wise manner until convergence of the core and pedestal plasmas is reached. This allows the evolution of the global plasma in response to small changes at the separatrix to be modelled, and offers a demonstration of how SOL properties can impact both the pedestal and global confinement. (author)

Part of:
26. IAEA Fusion Energy Conference. Programme, Abstracts and Conference Material

Additional details

Publishing Information

Imprint Title
26. IAEA Fusion Energy Conference. Programme, Abstracts and Conference Material
Imprint Pagination
935 p.
Journal Page Range
p. 179
Report number
IAEA-CN--234

Conference

Title
26. IAEA Fusion Energy Conference
Acronym
FEC 2016
Dates
17-22 Oct 2016
Place
Kyoto (Japan)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
49089349
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ASDEX TOKAMAK; BALLOONING INSTABILITY; CONVERGENCE; EDGE LOCALIZED MODES; HEATING; NITROGEN; PLASMA CONFINEMENT; PLASMA IMPURITIES; PLASMA SCRAPE-OFF LAYER; PLASMA SIMULATION; STABILITY; TRANSPORT THEORY
Descriptors DEC
BOUNDARY LAYERS; CLOSED PLASMA DEVICES; CONFINEMENT; ELEMENTS; IMPURITIES; INSTABILITY; LAYERS; NONMETALS; PLASMA INSTABILITY; PLASMA MACROINSTABILITIES; SIMULATION; THERMONUCLEAR DEVICES; TOKAMAK DEVICES

Optional Information

Notes
Abstract only
Secondary number(s)
IAEA-CN--234-0427