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In-vessel dust and tritium control strategy in ITER.

Authors :
Shimada, M.
Pitts, R.A.
Ciattaglia, S.
Carpentier, S.
Choi, C.H.
Dell Orco, G.
Hirai, T.
Kukushkin, A.
Lisgo, S.
Palmer, J.
Shu, W.
Veshchev, E.
Source :
Journal of Nuclear Materials. Jul2013 Supplement, Vol. 438, pS996-S1000. 0p.
Publication Year :
2013

Abstract

Abstract: A baseline strategy for dust and tritium-inventory control and recovery in ITER has been established and preparations are underway for its implementation. Limits on dust and tritium-inventory are an integral part of the ITER safety case and are fixed at 1kg for tritium, 1000kg for mobilisable dust and 11kg (beryllium)/76kg (tungsten) for dust on hot surfaces. Maximum average T-retention rates of ∼1g/shot are estimated for baseline inductive operation at QDT =10, suggesting that the in-vessel T-retention could reach the administrative limit of 640g in as little as ∼2months of operation. Baking is expected to remove a significant fraction of the T co-deposited on the divertor targets. Despite large uncertainties, dust quantities are expected to remain well below safety limits over the divertor cassette lifetime. In situ aspiration during divertor cassette exchange is foreseen as the main dust removal technique. [Copyright &y& Elsevier]

Details

Language :
English
ISSN :
00223115
Volume :
438
Database :
Academic Search Index
Journal :
Journal of Nuclear Materials
Publication Type :
Academic Journal
Accession number :
89303724
Full Text :
https://doi.org/10.1016/j.jnucmat.2013.01.217