Actively cooled plasma facing components for long pulse high power operation

Nygren, R.E.

doi:10.1016/s0920-3796(02)00009-1

Cited by 24 publications

(8 citation statements)

References 72 publications

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“…The current status of R&D on plasma facing materials and components are comprehensively summarized in recent review papers. [5][6][7][8][9] The followings are a brief summary of the currently promising options for ITER PFCs and non-destructive examinations applied during manufacturing.…”

Section: Plasma Facing Materials and Components In Itermentioning

confidence: 99%

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

2005

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The current ITER design employs beryllium, carbon fiber reinforced composite and tungsten as plasma facing materials. Since these materials are exposed to high heat fluxes during the operation, it is essential to perform high heat flux tests for R&D of ITER components. Static heat loads corresponding to cycling loads during normal operation, are estimated to be up to 20 MW/m 2 in the divertor targets and around 0.5 MW/m 2 at the first wall in ITER. For the static high heat flux testing, tests in electron beam facilities, particle beam facilities, IR heater and in-pile tests have been performed. Another type, more critical heat loads, which have high power densities and short durations, corresponding to transient events, i.e. plasma disruption, vertical displacement events (VDEs) and edge localized modes (ELMs) deliver considerable heat flux onto the plasma facing materials. For this purpose, tests in electron beam (short pulses), plasma gun and high power laser facilities have been carried out. The present work summarizes the features of these facilities and recent experimental results as well as the current selection of ITER plasma facing components.

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Section: Plasma Facing Materials and Components In Itermentioning

confidence: 99%

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

2005

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“…A swirl tape (thickness: 0.8 mm, twist ratio: 2) in the tube was assumed using modified empirical correlations of HTC [7][8][9] whereby complicated 3D CFD modelling was not required.…”

Section: Design Optimization Of the Iter-like Monoblockmentioning

confidence: 99%

Design study of ITER-like divertor target for DEMO

Crescenzi

Bachmann²,

Richou

et al. 2015

Fusion Engineering and Design

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“…A current problem in fusion reactor design is the selection of materials to be used for surfaces in close contact with the plasma. Conventional heat exchanger designs using water-cooled copper with an armor made of solid materials such as carbon, tungsten, and beryllium are unable to handle the expected heat flux of 10-30 MW/m 2 and are eroded by neutron bombardment 14,15 . Some proposed solutions to this problem involve replacing the solid surfaces with a flowing liquid 16 .…”

Section: Introductionmentioning

confidence: 99%

A Liquid Metal Flume for Free Surface Magnetohydrodynamic Experiments

Nornberg¹,

Ji²,

Peterson³

et al. 2008

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We present an experiment designed to study magnetohydrodynamic effects in free-surface channel flow.The wide aspect ratio channel (the width to height ratio is about 15) is completely enclosed in an inert atmosphere to prevent oxidization of the liquid metal. A custom-designed pump reduces entrainment of oxygen, which was found to be a problem with standard centrifugal and gear pumps. Laser Doppler Velocimetry experiments characterize velocity profiles of the flow. Various flow constraints mitigate secondary circulation and end effects on the flow. Measurements of the wave propagation characteristics in the liquid metal demonstrate the surfactant effect of surface oxides and the damping of fluctuations by a cross-channel magnetic field. 47.35.Tv, 52.72.+v,

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Actively cooled plasma facing components for long pulse high power operation

Cited by 24 publications

References 72 publications

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

Design study of ITER-like divertor target for DEMO

A Liquid Metal Flume for Free Surface Magnetohydrodynamic Experiments

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