Laser ablation and heating tests performed on Tore Supra and textor graphite samples

Proceedings - Symposium on Fusion Engineering

Volumn , Issue , 2003, Pages 96-99

  Le Guern, F ^a   Brygo, F ^a   Tabarant, M ^a   Lascoutouna, C ^a   Bellotto, N ^a   Hubert, C ^a   Weulersse, J M ^a  

^a DIF   (France)

Author keywords

[No Author keywords available]

Indexed keywords

DEPOSITION; DEUTERIUM; GRAPHITE; HEATING; LASER ABLATION; LASER PULSES; NANOSTRUCTURED MATERIALS; PLASMAS; STAINLESS STEEL; TRITIUM;

D-T FUSION REACTORS; HEATING TESTS; SPUTTERED PARTICLES;

FUSION REACTORS;

EID: 27644547452     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (4)

1. R. A. Causey, "Hydrogen isotope retention and recycling in fusion reactor plasma-facing components" Journal of Nuclear Materials 300 (2002) 91-117.
2. G. Federici et al, "In-vessel tritium retention and removal in ITER", Journal of Nuclear Materials 266-269 (1999) 14-29
3. C. H. Skinner et al., "Tritium removal from codeposits on carbon tiles by a scanning laser" Journal of Nuclear Materials 301 (2002) 98-107.
4. W. M. Shu et al., "Tritium decontamination of TFTR D-T plasma facing components using an ultra violet laser", Fusion Science and Technology, vol. 41, May 2002.