Testing of actively cooled mock-ups in several high heat flux facilities—An International Round Robin Test

Rödig, M.; Bobin-Vastra, I.; Cox, Simon; Escourbiac, F.; Gervash, A.; Kapoustina, A.; Kuehnlein, Walter L.; Кузнецов, В. Е.; Merola, M.; Nygren, R.E.; Youchison, D.L.

doi:10.1016/j.fusengdes.2005.06.212

Cited by 15 publications

(14 citation statements)

References 2 publications

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“…Consequently, it is very important to address the correlation of the evaluated results from different facilities since all of them have different machine parameters. To access the correlation between the results from different facilities, Round Robin Tests have been done by JUDITH, JEBIS, FE200, EBTS, TSEFFY and JET NBI Testbed 59,60) with the same nominal power density on the same mock-ups in those facilities. The main conclusion from these tests is that the surface temperatures evolution with power densities, fairly agreed with each other, although there were systematic deviation.…”

Section: Non-destructive Examinationmentioning

confidence: 99%

“…The detailed discussion on the deviation can be found in references. 59,60) The crucial points are (1) surface temperature measurement and (2) power density calibration. Calibration of surface temperature should have been done at each facility because of the different specification and alignment of optical thermometers (detecting wavelength, angle and window materials).…”

Section: Non-destructive Examinationmentioning

confidence: 99%

“…The well calibrated power density of neutral beam injector was used as reference power density in Round Robin Test. 60) …”

Section: Iter Relevant High Heat Flux Testing On Plasma Facing Surfacmentioning

confidence: 99%

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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: Non-destructive Examinationmentioning

confidence: 99%

Section: Non-destructive Examinationmentioning

confidence: 99%

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ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

2005

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“…These cover different design options (flat tile, monoblock) and different joining techniques for both, CFC and tungsten armor [3]. Mainly high power electron beam facilities [12] have been used for testing of these mock-ups by simulation of ITER relevant loading conditions.…”

Section: Thermal Fatigue Behavior Of Plasma Facing Componentsmentioning

confidence: 99%

Plasma-facing materials for thermo-nuclear fusion devices

Singheiser

Hirai

Linke

et al. 2009

Trans Indian Inst Met

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The plasma facing materials and components in existing and future fusion devices are strongly affected by plasma wall interaction processes. These components, in particular the first wall (FW), the limiters and the divertor are subject to intense quasi-stationary thermal loads during plasma operation. While the resulting thermal loads to the first wall will remain below 1 MW·m -2 , special attention has to be paid to high heat flux components like limiters and the divertor. Here the expected power densities will be at least one order of magnitude above the ones at the FW, with expected peak heat fluxes of up to 20 MW·m -2 for future magnetic confinement devices. Beside quasi-stationary heat loads, short transient thermal pulses with deposited energy densities up to several tens of MJ·m -2 are another serious concern for next step tokamak devices, in particular for ITER. The most serious events are plasma disruptions, vertical displacement events, and Edge Localized Modes (socalled ELMs). These requirements make high demands on the selection of qualified materials and reliable fabrication processes for actively cooled plasma facing components. High heat flux test facilities based on intense electron and ion beams have been utilized successfully to assess the efficiency and the fatigue life time of different material solutions and design concepts. Modeling and experiments with both normal operation scenarios and transient events, are being performed to evaluate and to quantify the resulting material erosion or damage and thus to assess the life time of the components. Additional research activities are focused on the degradation of materials and joints due to energetic neutrons. In order to investigate irradiation induced property changes, materials samples and actively cooled plasma facing components have been irradiated in fission reactors and tested in thermal load tests. The technical solutions which are considered today are mainly based on beryllium, carbon materials or tungsten as armor materials and copper alloys or stainless steel for the heat sink. Furthermore, the needs for extensive quality control methods and non-destructive analyses during the procurement phase will be highlighted.

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“…Table 1). Normal operation conditions on actively cooled components are mainly performed in electron or ion beam test facilities (Ref [157][158][159]. Electron beam devices use focused beams with diameters ranging from typically 1 to 10 mm; to provide homogeneous thermal loads to the full surface of the module and to control the pattern size and shape, fast beam scanning modes (e.g., saw tooth-filled, triangular-filled rectangles or TV-raster scans with flyback) are applied.…”

Section: High Heat Flux Testingmentioning

confidence: 99%

Thermal Spray Coatings for Fusion Applications—Review

2007

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Thermonuclear fusion is a potential source of cleaner and safer energy for the future. Its technological realization depends on the development of materials able to survive and function in extreme conditions. This article reviews the applications of thermally sprayed coatings for fusion reactor materials. First, the principle and purpose of fusion is briefly introduced, and technological objectives are mentioned. Material-environment interactions are summarized, together with materials requirements and the role of coatings. Then, specific applications-e.g., the plasma facing components-are reviewed, focusing on application issues as well as issues related to thermal spray processing and specific properties of the respective materials. An overview of specific materials testing methods is also provided.

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Testing of actively cooled mock-ups in several high heat flux facilities—An International Round Robin Test

Cited by 15 publications

References 2 publications

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

Plasma-facing materials for thermo-nuclear fusion devices

Thermal Spray Coatings for Fusion Applications—Review

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