Title :
Tritium consumption and retention in TFTR neutral beams
Author :
Kamperschroer, J.H. ; Cropper, M.B. ; Grisham, A. ; McCormack, B.E. ; Nagy, Akos ; O´Connor, T.E. ; Oldaker, M.E. ; Stevenson, T.N. ; von Halle, A.
Author_Institution :
Plasma Phys. Lab., Princeton Univ., NJ, USA
Abstract :
750,000 Ci of tritium have passed through the TFTR neutral beamlines since December, 1993. During the course of 725 tritium heated discharges, 47,000 Ci have been extracted as ions from the ion sources and 27,000 Ci injected into TFTR as neutral atoms. Prior to the commencement of deuterium-tritium (DT) experiments, Los Alamos and Sandia National Laboratories made estimates of tritium retention in each beamline due to implantation in the 2 m2 of copper beam absorbers and absorption on the 250 m2 of internal surface area. Their estimates were: 500 Ci embedded per beamline in beam absorbers after 1000 DT Shots; and 100 Ci adsorbed per beamline after exposure to 1 torr of tritium for 1 hour. Both estimates were revised downward since the estimates assumed pure tritium operation, whereas the neutral beams used orders of magnitude more deuterium than tritium. Deuterium competes with tritium for implantation and adsorption sites, reducing the uptake of tritium relative to the use of pure tritium. Data from neutron detectors indicated that the quantity of tritium implanted is equivalent to the revised estimate. The amount of adsorbed tritium exceeds the prediction. While tritium operation was highly successful, there were problems with the failure of several ion sources and gas injectors. Ion source failures were not due to the use of tritium as the working gas. However, their removal yielded information regarding tritium retention. Ten tritium injectors failed during the three and a half years of tritium experiments; six were replaced. At the conclusion of TFTR operation, all working tritium injectors had throughput leaks. By comparison, the deuterium injectors, which used the same valves, had only two minor fill valve leaks, and no repairs were necessary. Tritium contaminated component removal required purging until the concentration of tritium in any released air was <20 μ Ci/m3. For ion source removal this necessitated 50 to 100 purges and the release of several Ci. Upon removal, source surfaces had to be further decontaminated, from several million dpm/100 cm2 to levels at which repairs could be effected
Keywords :
Tokamak devices; fusion reactor fuel; tritium; 750000 Ci; Cu beam absorbers; D; T; T consumption; T retention; TFTR; deuterium injectors; neutral beamline; repair; tritium injectors; Absorption; Copper; Detectors; Deuterium; Fault location; Ion sources; Laboratories; Neutrons; Throughput; Valves;
Conference_Titel :
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Conference_Location :
San Diego, CA
Print_ISBN :
0-7803-4226-7
DOI :
10.1109/FUSION.1997.687809