Published October 2010 | Version v1
Report

Effect of ELM Mitigation on Confinement and Divertor Heat Loads on JET

  • 1. EFDA-JET CSU, Culham Science Centre, OX14 3DB, Abingdon (United Kingdom)
  • 2. Laboratorio Nacional de Fusion, Asociacion EURATOM-CIEMAT, Madrid (Spain)
  • 3. Max-Planck-Instiut fur Plasmaphysik, EURATOM-Assoziation, Greifswald (Germany)
  • 4. Fusion for Energy Joint Undertaking, 08019, Barcelona (Spain)
  • 5. Max-Planck-Institut fur Plasmaphysik, EURATOM-Assoziation, Garching (Germany)
  • 6. EURATOM-CCFE Fusion Association, Culham Science Centre, Abingdon (United Kingdom)

Description

Full text: In JET several techniques have successfully demonstrated their capability for ELM amelioration (reduction of ELM losses and increase of ELM frequency), including resonant perturbations of the edge magnetic field by using the error field correction coils (EFCCs) and ELM magnetic triggering by fast vertical movements of the plasma column (vertical kicks). In this paper we present a summary of recent dedicated experiments in JET focused on integrating kicks and EFCCs into similar plasma scenario and scans in order to compare their performance. The impact of each control method on the plasma confinement and the effect of the reduction in ELM size on the divertor heat loads have been studied. In addition, the potential of using EFCCs for ELM mitigation in He4 plasmas has also been explored in JET, and a comparison of those results with the effects observed in D plasmas is included in this paper. The plasma response to the application of these two ELM control methods in D plasmas shares common features: the reduction in ELM size is accompanied by a reduction in pedestal pressure (mainly due to a loss in density), resulting in a 10% reduction of the thermal stored energy. A key ingredient in the ELM mitigation experiments in JET is the diagnosis of the ELM-resolved divertor heat load profiles on the outer target by a fast high resolution infrared camera. It was found that the averaged ELM peak-power decreases almost linearly with the ELM size, but a smaller reduction is observed on the peak heat flux (40% for EFCCs when the reduction in peak power is ∼ 50%). This difference is related to a reduction in the width of the ELM heat flux profile. This observation is common to any small ELM regime, independently of the method employed to reduce the ELMs size (gas fuelling, kicks or EFCCs and also enhanced toroidal ripple). Interestingly, in the case of kicks or EFCCs the reduction in ELM losses is accompanied by some pedestal density loss, resulting in low pedestal collisionality. In contrast, a stronger reduction in the peak heat flux is observed in gas fuelled plasmas, where the reduction in ELM losses is correlated with an increase in collisionality. A detailed analysis of the divertor heat loads for mitigated ELMs will be compared to the analysis done for the database of spontaneous ELMs in JET. The implications of these new data for ITER will be discussed. (author)

Part of:
23. IAEA Fusion Energy Conference. Book of Abstracts

Additional details

Publishing Information

Imprint Title
23. IAEA Fusion Energy Conference. Book of Abstracts
Imprint Pagination
637 p.
Journal Page Range
p. 53
Report number
IAEA-CN--180

Conference

Title
23. IAEA Fusion Energy Conference
Acronym
FEC 2010
Dates
11-16 Oct 2010
Place
Daejeon (Korea, Republic of)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
43040750
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPARATIVE EVALUATIONS; DIVERTORS; EDGE LOCALIZED MODES; GAS FUELS; HEAT FLUX; HEATING LOAD; ITER TOKAMAK; MAGNETIC FIELDS; MITIGATION; PEAK LOAD; PERTURBATION THEORY; PLASMA; PLASMA CONFINEMENT
Descriptors DEC
CLOSED PLASMA DEVICES; CONFINEMENT; EVALUATION; FUELS; INSTABILITY; PLASMA INSTABILITY; PLASMA MACROINSTABILITIES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Collaborations
JET-EFDA Contributors
Secondary number(s)
EXC--8-4