EU Development of High Heat Flux Components

Journal Article · Fri Apr 15 00:00:00 EDT 2005 · Fusion Science and Technology

OSTI ID:20849943

Linke, J ^[1]; Lorenzetto, P ^[2]; Majerus, P ^[1]; Merola, M ^[2]; Pitzer, D ^[1]; Roedig, M ^[1]

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1. Forschungszentrum Juelich GmbH (Germany)
2. EFDA Close Support Unit Garching (Germany)

The development of plasma facing components for next step fusion devices in Europe is strongly focused to ITER. Here a wide spectrum of different design options for the divertor target and the first wall have been investigated with tungsten, CFC, and beryllium armor. Electron beam simulation experiments have been used to determine the performance of high heat flux components under ITER specific thermal loads. Beside thermal fatigue loads with power density levels up to 20 MWm{sup -2}, off-normal events are a serious concern for the lifetime of plasma facing components. These phenomena are expected to occur on a time scale of a few milliseconds (plasma disruptions) or several hundred milliseconds (vertical displacement events) and have been identified as a major source for the production of neutron activated metallic or tritium enriched carbon dust which is of serious importance from a safety point of view.The irradiation induced material degradation is another critical concern for future D-T-burning fusion devices. In ITER the integrated neutron fluence to the first wall and the divertor armour will remain in the order of 1 dpa and 0.7 dpa, respectively. This value is low compared to future commercial fusion reactors; nevertheless, a nonnegligible degradation of the materials has been detected, both for mechanical and thermal properties, in particular for the thermal conductivity of carbon based materials. Beside the degradation of individual material properties, the high heat flux performance of actively cooled plasma facing components has been investigated under ITER specific thermal and neutron loads.

• OSTI ID: 20849943
• Journal Information: Fusion Science and Technology, Vol. 47, Issue 3; Other Information: Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/; Country of input: International Atomic Energy Agency (IAEA); ISSN 1536-1055
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
ATOMIC DISPLACEMENTS
BERYLLIUM
CARBON
COMPUTERIZED SIMULATION
DIVERTORS
ELECTRON BEAMS
FIRST WALL
HEAT FLUX
IRRADIATION
ITER TOKAMAK
NEUTRON FLUENCE
NEUTRONS
PERFORMANCE
PLASMA DISRUPTION
POWER DENSITY
THERMAL CONDUCTIVITY
THERMAL FATIGUE
THERMONUCLEAR REACTOR MATERIALS
TRITIUM
TUNGSTEN