Efficiency of thermal outgassing for tritium retention measurement and removal in ITER. (August 2017)

• Record Type: Journal Article
• Authors: De Temmerman, G.; Baldwin, M.J.; Anthoine, D.; Heinola, K.; Jan, A.; Jepu, I.; Likonen, J.; Lungu, C.P.; Porosnicu, C.; Pitts, R.A.
• Is Part Of: Nuclear materials and energy. Volume 12(2017)
• Page Start: 267
• Page End: 272
• Publication Date: 2017-08
• Subjects: Tritium retention -- ITER -- Divertor -- Outgassing; Nuclear energy -- Periodicals; Nuclear fuels -- Periodicals; Nuclear reactors -- Materials -- Periodicals; Radioactive substances -- Periodicals; 621.4833
• DOI: 10.1016/j.nme.2016.10.016
• Languages: English
• ISSNs: 2352-1791

Abstract

Abstract: As a licensed nuclear facility, ITER must limit the in-vessel tritium (T) retention to reduce the risks of potential release during accidents, the inventory limit being set at 1 kg. Simulations and extrapolations from existing experiments indicate that T-retention in ITER will mainly be driven by co-deposition with beryllium (Be) eroded from the first wall, with co-deposits forming mainly in the divertor region but also possibly on the first wall itself. A pulsed Laser-Induced Desorption (LID) system, called Tritium Monitor, is being designed to locally measure the T-retention in co-deposits forming on the inner divertor baffle of ITER. Regarding tritium removal, the baseline strategy is to perform baking of the plasma-facing components, at 513 K for the FW and 623 K for the divertor. Both baking and laser desorption rely on the thermal desorption of tritium from the surface, the efficiency of which remains unclear for thick (and possibly impure) co-deposits. This contribution reports on the results of TMAP7 studies of this efficiency for ITER-relevant deposits.