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Comparison of tokamak behaviour with tungsten and low-Z plasma facing materials
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2000 (English)In: Plasma Physics and Controlled Fusion, ISSN 0741-3335, E-ISSN 1361-6587, Vol. 42, B293-B310 p.Article in journal (Refereed) Published
Abstract [en]

Graphite wall materials are used in present day fusion devices in order to optimize plasma core performance and to enable access to a large operational space. A large physics database exists for operation with these plasma facing materials, which also indicate their use in future devices with extended burn times. The radiation from carbon impurities in the edge and divertor regions strongly helps to reduce the peak power loads on the strike areas, but carbon radiation also supports the formation of MARFE instabilities which can hinder access to high densities. The main concerns with graphite are associated with its strong chemical affinity to hydrogen, which leads to chemical erosion and to the formation of hydrogen-rich carbon layers. These layers can store a significant fraction of the total tritium fuel, which might prevent the use of these materials in future tritium devices. High-Z plasma facing materials are much more advantageous in this sense, but these advantages compete with the strong poisoning of the plasma if they enter the plasma core. New promising experiences have been obtained with high-Z wall materials in several devices, about which a survey is given in this paper and which also addresses open questions for future research and development work.

Place, publisher, year, edition, pages
2000. Vol. 42, B293-B310 p.
Keyword [en]
asdex upgrade, hydrocarbon formation, divertor experiment, pyrolytic-graphite, fusion devices, surfaces, erosion, carbon, temperatures, discharges
URN: urn:nbn:se:kth:diva-20262DOI: 10.1088/0741-3335/42/12B/322ISI: 000166145300024OAI: diva2:338956
QC 20100525Available from: 2010-08-10 Created: 2010-08-10Bibliographically approved

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Rubel, Marek J.
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Alfvén Laboratory
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