Published 2008 | Version v1
Report

Divertor heat loads due to edge localized modes in ASDEX Upgrade and JET

Creators

  • 1. IPP-Garching, Garching bei Muenchen (Germany)

Description

Transient power loads due to ELMs are a major concern for the life time of divertor tiles in ITER, irrespective of the choice of plasma facing material. Large ELMs cause enhanced material erosion (ablation, evaporation) possibly leading to unacceptable impurity influx, radiation and fuel dilution in the plasma core. Significant progress has been made towards a physics-based model describing Type-I ELM energy transport to the divertor and the first wall. Specifically, the temporal evolution of infra-red measured divertor heat loads due to Type-I ELMs on ASDEX Upgrade (AUG) is well reproduced by an analytic formula representing the arrival of ions originating at the outer midplane with a Maxwellian velocity distribution characterized by only the pedestal. For large Type-I ELMs in JET (100-600 kJ, 5-20 % pedestal energy) and ASDEX Upgrade (6-20 kJ, 3-10 % pedestal energy) the ELM power deposition time on the inner/outer divertor targets is dependent only on the corresponding parallel ion transit time. In particular, for low pedestal collisionality (as expected in ITER), it predicts ELM power deposition time of 1.2 times the parallel transport time which yields a power deposition time of 280 μ s at the ITER pedestal temperature. The analysis of JET and ASDEX Upgrade data also reveals the temporal hierarchy of ELM energy release, parallel transport and power deposition time. On JET, the fraction of energy of deposited on the target within the duration of the power deposition time varies between 20% for the largest ELMs (lowest pedestal collisionality) and to 35% for smallest ELMs (highest pedestal collisionality). It is noteworthy in that respect that the found temporal hierarchy of ELM energy release, parallel transport and power deposition time is broken for the much smaller (and more collisional) Type- III ELMs. For these ELMs, both quantities ELM energy release time and parallel transport have to be taken into account when estimating the resulting ELM peak heat fluxes. The above results confirm the previous, purely empirical scaling, on the type-I ELM power deposition times. However, combined with recent material test, the formerly calculated limit of a maximum ELM energy loss in ITER is revised and a significantly lower value of about 1-2 MJ is found. Therefore, some form of ELM mitigation techniques appears to be mandatory for ITER. (author)

Part of:
22. IAEA fusion energy conference: 'Celebrating fifty years of fusion... entering into the burning plasma era'. Book of abstracts

Additional details

Publishing Information

Imprint Title
22. IAEA fusion energy conference: 'Celebrating fifty years of fusion... entering into the burning plasma era'. Book of abstracts
Imprint Pagination
295 p.
Journal Page Range
p. 11
Report number
INIS-XA--08N0893

Conference

Title
22. IAEA fusion energy conference : 'Celebrating fifty years of fusion... entering into the burning plasma era'
Acronym
FEC 2008
Dates
13-18 Oct 2008
Place
Geneva (Switzerland)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
39116422
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ABLATION; ASDEX TOKAMAK; DEPOSITION; DISTRIBUTION; DIVERTORS; EDGE LOCALIZED MODES; ENERGY LOSSES; EROSION; FIRST WALL; HEAT FLUX; HEATING LOAD; ITER TOKAMAK; PLASMA; PLASMA IMPURITIES
Descriptors DEC
CLOSED PLASMA DEVICES; IMPURITIES; INSTABILITY; LOSSES; PLASMA INSTABILITY; PLASMA MACROINSTABILITIES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Secondary number(s)
EX/4--3Rb