Efficiency of thermal outgassing for tritium retention measurement and removal in ITER

Bibliographic Details
Title: Efficiency of thermal outgassing for tritium retention measurement and removal in ITER
Authors: G. De Temmerman, M.J. Baldwin, D. Anthoine, K. Heinola, A. Jan, I. Jepu, J. Likonen, C.P. Lungu, C. Porosnicu, R.A. Pitts
Source: Nuclear Materials and Energy, Vol 12, Iss , Pp 267-272 (2017)
Publisher Information: Elsevier, 2017.
Publication Year: 2017
Collection: LCC:Nuclear engineering. Atomic power
Subject Terms: Nuclear engineering. Atomic power, TK9001-9401
More Details: 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 1kg. 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 513K for the FW and 623K 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. keywords: Tritium retention, ITER, Divertor, Outgassing
Document Type: article
File Description: electronic resource
Language: English
ISSN: 2352-1791
Relation: http://www.sciencedirect.com/science/article/pii/S2352179116301284; https://doaj.org/toc/2352-1791
DOI: 10.1016/j.nme.2016.10.016
Access URL: https://doaj.org/article/c5f267c71db646329c39616a0143740a
Accession Number: edsdoj.5f267c71db646329c39616a0143740a
Database: Directory of Open Access Journals
More Details
ISSN:23521791
DOI:10.1016/j.nme.2016.10.016
Published in:Nuclear Materials and Energy
Language:English