Tungsten coatings under fusion relevant heat loads

Components for first wall applications in future nuclear fusion devices like ITER or DEMO need to fulfill special requirements. Especially transient thermal loads like Edge Localized Modes (ELMs) have a severe impact on the material damage. Tungsten coatings are being assessed for use instead of bul...

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Дата:2010
Автори: Thomser, C., Linke, J., Matthews, G., Riccardo, V., Schmidt, A., Vasechko, V.
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Мова:Англійська
Опубліковано: Національний науковий центр «Харківський фізико-технічний інститут» НАН України 2010
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Назва журналу:Digital Library of Periodicals of National Academy of Sciences of Ukraine
Цитувати:Tungsten coatings under fusion relevant heat loads / C. Thomser, J. Linke, G. Matthews, V. Riccardo, A. Schmidt, V. Vasechko // Вопросы атомной науки и техники. — 2010. — № 6. — С. 54-56. — Бібліогр.: 1 назв. — англ.

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Digital Library of Periodicals of National Academy of Sciences of Ukraine
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author Thomser, C.
Linke, J.
Matthews, G.
Riccardo, V.
Schmidt, A.
Vasechko, V.
author_facet Thomser, C.
Linke, J.
Matthews, G.
Riccardo, V.
Schmidt, A.
Vasechko, V.
citation_txt Tungsten coatings under fusion relevant heat loads / C. Thomser, J. Linke, G. Matthews, V. Riccardo, A. Schmidt, V. Vasechko // Вопросы атомной науки и техники. — 2010. — № 6. — С. 54-56. — Бібліогр.: 1 назв. — англ.
collection DSpace DC
description Components for first wall applications in future nuclear fusion devices like ITER or DEMO need to fulfill special requirements. Especially transient thermal loads like Edge Localized Modes (ELMs) have a severe impact on the material damage. Tungsten coatings are being assessed for use instead of bulk tungsten. In order to quantify their material degradation, tungsten coatings on a fiber-reinforced graphite substrate were exposed to repeated short fusion relevant thermal pulses in an electron beam material test facility JUDITH 1 (Juelich Divertor Test Facility in Hot Cells).
first_indexed 2025-12-07T18:56:55Z
format Article
fulltext 54 PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. 2010. 6. Series: Plasma Physics (16), p. 54-56. TUNGSTEN COATINGS UNDER FUSION RELEVANT HEAT LOADS C. Thomser1, J. Linke1, G. Matthews2, V. Riccardo2, A. Schmidt1, V. Vasechko1 1Forschungszentrum Jülich EURATOM-Association FZJ, D-52425 Jülich, Germany; 2Euratom/UKAEA Fusion Association, Culham Science Centre, Abingdon, UK E-mail: c.thomser@fz-juelich.de Components for first wall applications in future nuclear fusion devices like ITER or DEMO need to fulfill special requirements. Especially transient thermal loads like Edge Localized Modes (ELMs) have a severe impact on the material damage. Tungsten coatings are being assessed for use instead of bulk tungsten. In order to quantify their material degradation, tungsten coatings on a fiber-reinforced graphite substrate were exposed to repeated short fusion relevant thermal pulses in an electron beam material test facility JUDITH 1 (Juelich Divertor Test Facility in Hot Cells). PACS: 28.52.Fa 1. INTRODUCTION First wall components for applications in future nuclear fusion devices need to fulfil special requirements, e.g. a good thermal conductivity, a reasonable strength value as well as a good compatibility with a deuterium / tritium plasma. Moreover neutron irradiation has not to lead to an unacceptable activation and a significant degradation of material properties. Especially transient and / or cyclic thermal loads in magnetic confinement experiments like ITER have a severe impact on the material damage of the plasma facing components. Tungsten coatings are being assessed for use instead of bulk tungsten components. Within the ITER like wall project, realised at JET, a part of the thermally loaded wall will consist of tungsten coated CFC modules. In order to quantify the material degradation under transient ELM – like heat loads (Edge Localised Modes), tungsten coatings on a fibre-reinforced graphite substrate were exposed to short fusion relevant thermal pulses in the electron beam material test facility JUDITH 1 (Juelich Divertor Test Facility in Hot Cells). In addition the failure mechanism of the coatings was investigated. 2. THERMAL SHOCK TESTS The applied test parameters for the thermal shock tests in the electron beam facility JUDITH 1 are as follows: - Sample size: 12 x 12 x 5 mm - Absorbed power densities: 79…316 MW/m2 - Electron absorption coefficient: 0.46 - Base temperature: 22…400 °C - Loaded area: 4 x 4 mm - Pulse duration: 1 ms - Inter pulse time: 2 s - Beam scanning frequency (x / y): 31 kHz / 40 kHz - Number of pulses: 100 - Electron beam diameter: 1 mm A picture of the electron beam facility JUDITH 1 is presented in Fig. 1. Fig. 1. Electron beam material test device JUDITH 1 3. MATERIAL A cross – section of the tested coating is presented in Fig. 2. The coating has a total thickness of 20…25 µm and consists of a double layer structure of tungsten and molybdenum. The coating was produced by a Combined Magnetron Sputtering and Ion Implantation (CMSII) coating technique in Romania [1]. Fig. 2. Cross section of the tungsten coating 4. RESULTS The delamination of the coating starts at absorbed power densities of about 158 MW/m2 for nearly the whole range of investigated temperatures. With increasing power density material degradation is increasing. Delamination always begins on the parallel fibers of the CFC substrate, like it is shown in the SEM picture in Fig.3. 25 µm tungstenmolybdenum CFC substrate Dunlop DMS 780 mailto:c.thomser@fz-juelich.de 55 Fig. 3. SEM picture of the delamination of the coating, 158 MW/m2, 1 ms, 100 shots, room temperature In Fig. 4 and Fig.5 additionally crack formation and melting for different loading conditions are presented. Fig. 4. SEM picture of the failure of the coating, 158 MW/m2, 1 ms, 100 shots, base temperature 100 °C Fig. 5. SEM picture of the failure of the coating, 237 MW/m2, 1 ms, 100 shots, base temperature 100 °C An overview about the failure occurrence in dependence on the absorbed power density and base temperature is given in Fig. 6. 0 100 200 300 400 500 0 100 200 300 400 500 Base temperature, °C A bs or be d po w er d en si ty , M W /m 2 No damage Surface modification Cracking Delamination and cracking Delamination, cracking and melting Fig. 6. Overview about the damage mechanisms of the tungsten coating Only a small influence of base temperature can be observed especially for the highest absorbed power density. With increasing temperature the delaminated area is decreasing (two samples are shown as an example in Fig. 7). However, the temperature influence seems not to play the major role for the degradation of the coating. delaminated area Fig. 7. Influence of temperature on the delamination of the coating, 316 MW/m2, 1 ms, 100 shots Moreover, spark erosion is documented by an optical camera in the first shot of the experiments. The exposure time was 5 s, i.e. the trajectories of all ejected particles are recorded in the photographs. Almost no erosion can be found at power densities below 158 MW/m2. For higher power densities heavy spark erosion is observed, which a hint for the delamination of the coating is. The magnitude of spark erosion is dependent on the absorbed power density, like it is presented for two examples in Fig. 8 and 9. Fig. 8. Spark erosion, absorbed power density 237 MW/m2, 1 ms, 100 shots, room temperature 12 mm 400 °C 100 °C delaminated parallel CFC fiber tungsten coating delamination cracking delamination cracking melting 56 Fig. 9. Spark erosion, absorbed power density 316 MW/m2, 1 ms, 100 shots, room temperature 5. CONCLUSIONS The damage threshold and the failure mechanism of tungsten coatings under transient fusion relevant heat loads were characterised in an electron beam facility. The delamination of the coating is mainly dependent on the absorbed power density. Only a very small influence of temperature can be observed. The parallel fiber orientation of the CFC substrate is the preferred region to start the delamination of the coating due to the bad thermal conductivity and the high mismatch in thermal expansion between the coating and the substrate. ACKNOWLEDGEMENTS We acknowledge G. Knauf, G. Böling, T. Flossdorf, E. Wessel, M. Diederichs, M. Hühnerbein and M. Wirtz for their assistance with the experiments and investigations. This work, supported by the European Communities under the contract of Association between EURATOM/Forschungszentrum Jülich, was carried out within the framework of the European Fusion Development Agreement. The views and opinions expressed herein do not necessarily reflect those of the European Commission. REFERENCES 1. C. Ruset, et al.// Fusion Engineering and Design. 2009, v. 84, p. 1662. Article received 13.09.10 , . , . , . , . , . , . ITER DEMO . (ELM). . , , , , , (JUDITH 1 . ). , . , . , . , . , . , . ITER DEMO . (ELM). . , , , , , (JUDITH 1, . ).
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institution Digital Library of Periodicals of National Academy of Sciences of Ukraine
issn 1562-6016
language English
last_indexed 2025-12-07T18:56:55Z
publishDate 2010
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spelling Thomser, C.
Linke, J.
Matthews, G.
Riccardo, V.
Schmidt, A.
Vasechko, V.
2011-02-26T20:52:56Z
2011-02-26T20:52:56Z
2010
Tungsten coatings under fusion relevant heat loads / C. Thomser, J. Linke, G. Matthews, V. Riccardo, A. Schmidt, V. Vasechko // Вопросы атомной науки и техники. — 2010. — № 6. — С. 54-56. — Бібліогр.: 1 назв. — англ.
1562-6016
https://nasplib.isofts.kiev.ua/handle/123456789/17457
Components for first wall applications in future nuclear fusion devices like ITER or DEMO need to fulfill special requirements. Especially transient thermal loads like Edge Localized Modes (ELMs) have a severe impact on the material damage. Tungsten coatings are being assessed for use instead of bulk tungsten. In order to quantify their material degradation, tungsten coatings on a fiber-reinforced graphite substrate were exposed to repeated short fusion relevant thermal pulses in an electron beam material test facility JUDITH 1 (Juelich Divertor Test Facility in Hot Cells).
We acknowledge G. Knauf, G. Böling, T. Flossdorf, E. Wessel, M. Diederichs, M. Hühnerbein and M. Wirtz for their assistance with the experiments and investigations. This work, supported by the European Communities under the contract of Association between EURATOM/Forschungszentrum Jülich, was carried out within the framework of the European Fusion Development Agreement. The views and opinions expressed herein do not necessarily reflect those of the European Commission.
en
Національний науковий центр «Харківський фізико-технічний інститут» НАН України
ИТЭР и приложения для термоядерного реактора
Tungsten coatings under fusion relevant heat loads
Поведение вольфрамовых покрытий в условиях, имитирующих термоядерные тепловые нагрузки
Article
published earlier
spellingShingle Tungsten coatings under fusion relevant heat loads
Thomser, C.
Linke, J.
Matthews, G.
Riccardo, V.
Schmidt, A.
Vasechko, V.
ИТЭР и приложения для термоядерного реактора
title Tungsten coatings under fusion relevant heat loads
title_alt Поведение вольфрамовых покрытий в условиях, имитирующих термоядерные тепловые нагрузки
title_full Tungsten coatings under fusion relevant heat loads
title_fullStr Tungsten coatings under fusion relevant heat loads
title_full_unstemmed Tungsten coatings under fusion relevant heat loads
title_short Tungsten coatings under fusion relevant heat loads
title_sort tungsten coatings under fusion relevant heat loads
topic ИТЭР и приложения для термоядерного реактора
topic_facet ИТЭР и приложения для термоядерного реактора
url https://nasplib.isofts.kiev.ua/handle/123456789/17457
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