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Abstract

Until the construction of the Mk1 divertor it had been usual practice to perform a high pressure water wash of the inside of the Joint European Torus (JET) vacuum vessel. The purpose of these washes were to remove contamination generated during the work itself and so reduce any adverse effects on plasma performance. These washes were not designed to remove beryllium or reduce in any way the respiratory protection requirements during work in the vessel. The construction of the pumped divertor has now made the use of water as a washing medium unsuitable. Prior to the installation of the Mk1 divertor alternative cleaning methods were examined and one which showed potential was carbon dioxide pellet blasting. After a number of trials were performed it was decided that the vessel should be cleaned using this method after completion of the divertor coil build. How it was carried out, what results were obtained and its potential future use are discussed in this report.

Additional information

Authors: SCOTT S M, JET Joint Undertaking, Abingdon, Oxon (GB);HAIGH A, JET Joint Undertaking, Abingdon, Oxon (GB);SCHREIBMAIER J, JET Joint Undertaking, Abingdon, Oxon (GB);DAVIES N, JET Joint Undertaking, Abingdon, Oxon (GB);PORTER A, JET Joint Undertaking, Abingdon, Oxon (GB);SAIBENE G, JET Joint Undertaking, Abingdon, Oxon (GB)
Bibliographic Reference: Article : Plasma Physics and Controlled Fusion (1995)
Record Number: 199512131 / Last updated on: 1996-01-15
Category: PUBLICATION
Original language: en
Available languages: en