Study on divertor materials and heat load experiments with electron beam facility

Typical heat load conditions on a divertor plate in a fusion reactor are 2 MW/m 2 at normal operation and 500 MW/m 2 × 5 ms at plasma disruption. Test Materials I and II were prepared for basic material tests, corresponding to the followings, (1) Design I: tube structure of copper alloy with or with...

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Bibliographic Details
Published inJournal of nuclear materials Vol. 141; pp. 204 - 209
Main Authors Ioki, K., Yamada, M., Nishikawa, M., Uchikawa, T., Yamao, H.
Format Journal Article
LanguageEnglish
Published Elsevier B.V 01.11.1986
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Summary:Typical heat load conditions on a divertor plate in a fusion reactor are 2 MW/m 2 at normal operation and 500 MW/m 2 × 5 ms at plasma disruption. Test Materials I and II were prepared for basic material tests, corresponding to the followings, (1) Design I: tube structure of copper alloy with or without protection layer, and (2) Design II: graphite tiles brazed to a metal tube. Test Material I is a plate of a OMC Cu-Cr-Zr alloy. The molybdenum coating (∼500 μm) was applied by plasma spray. Test Material II is graphite brazed to a molybdenum base plate. Heat load experiments were performed on the test materials for normal operation or disruption simulation by using a 120 kW electron beam facility. Thermomechanical and erosion analyses were also performed. This basic study showed that these two types of materials have good characteristics at the typical heat load conditions.
Bibliography:ObjectType-Article-2
SourceType-Scholarly Journals-1
ObjectType-Feature-1
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ISSN:0022-3115
1873-4820
DOI:10.1016/S0022-3115(86)80037-X