Title :
Tritium decontamination of TFTR D-T graphite tiles employing ultra violet light and a Nd:YAG laser
Author :
Gentile, C.A. ; Skinner, C.H. ; Young, K.M. ; Ciebiera, L. ; Langish, S.W. ; von Halle, A. ; Kennedy, C.W. ; O´hira, S. ; Shu, W.M.
Author_Institution :
Plasma Phys. Lab., Princeton Univ., NJ, USA
Abstract :
The use of an ultra violet light source (wavelength=172 nm) and a Nd:YAG laser for the decontamination of TFTR D-T tiles will be investigated at PPPL. The development of this form of tritium decontamination may be useful for future D-T burning fusion devices which employ carbon plasma facing components on the first wall. Carbon tiles retain hydrogen isotopes, and the in-situ tritium decontamination of carbon can be extremely important in maintaining resident in-vessel tritium inventory to a minimum. A test chamber has been designed and fabricated at PPPL. The chamber has the ability to be maintained under vacuum, be baked to 200°C. and provides sample ports for gas analyses. Tiles from TFTR that have been exposed to D-T plasmas will be placed within the chamber and exposed to either UV light source or the ND:YAG Laser. The experiment will determine the effectiveness of these two techniques for the removal of tritium. In addition, exposure rates and scan times for the UV light source and/or Nd:YAG laser will be determined for tritium removal optimization from D-T tiles
Keywords :
Tokamak devices; deuterium; fusion reactor fuel; graphite; tritium; ultraviolet radiation effects; 172 nm; 200 degC; C; D-T; D-T graphite tiles; Nd:YAG laser; T decontamination; TFTR; UV light source; YAG:Nd; YAl5O12:Nd; ultra violet light; Decontamination; Hydrogen; Isotopes; Laser fusion; Light sources; Plasma devices; Plasma sources; Plasma waves; Testing; Tiles;
Conference_Titel :
Fusion Engineering, 1999. 18th Symposium on
Conference_Location :
Albuquerque, NM
Print_ISBN :
0-7803-5829-5
DOI :
10.1109/FUSION.1999.849847