Showing 1 - 2 of 2 UKAEA Paper Results
2005
T.Tanabe K.Sugiyama C.H.Skinner N.Bekris C.A.Gentile J.P. Coad
Tritium accumulating in codeposits in the gaps between plasma facing components is a safety concern in next step fusion machines as suitable removal techniques have yet not been developed. We report on Imaging Plate measurements of the tritium areal distribution on the side surface of graphite/CFC tiles installed in the TFTR bumper limiter and JET …
Published2005
A. Perevezentsev A. Bell D. Brennan A. Miller A. Healer C. Gentile L. Ciebiera S. Langish
Operation with tritium plasma led to contamination of the JET in-vessel components with tritium at a level exceeding 12kBq/g, which is the Low Level Waste (LLW) threshold in the UK. Carbon tiles used at JET for protecting the pumped divertor and inner wall against heat and neutron flux create one of the Intermediate Level Waste (ILW) streams to dea…
Published