Modelling of tritium retention and target lifetime of the ITER divertor

A. Kirschner, S. Droste, D. Borodin, V. Philipps, U. Samm, G. Federici, J. Roth

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

Erosion, deposition and transport of eroded material in the divertor of ITER are modelled with the Monte Carlo impurity transport code ERO taking into account chemical erosion, physical sputtering, enhanced erosion of redeposited carbon and beryllium deposition. With increasing exposure time continuous deposition of beryllium leads to reduced carbon erosion along the divertor plates. The limit of discharges possible from the estimated long-term tritium retention ranges between 440 using an effective sticking of unity for redeposited hydrocarbons and 380 for an effective sticking of zero. The lifetime of the divertor plates is less critical than tritium-retention, in the worst case about 7000 ITER discharges. Erosion due to transient heat loads (ELMs or disruptions) are not yet included in the modelling.

Original languageEnglish
Title of host publication32nd EPS Conference on Plasma Physics 2005, EPS 2005, Held with the 8th International Workshop on Fast Ignition of Fusion Targets - Europhysics Conference Abstracts
Pages353-356
Number of pages4
StatePublished - 2005
Externally publishedYes
Event32nd European Physical Society Conference on Plasma Physics and Controlled Fusion combined with the 8th International Workshop on Fast Ignition of Fusion Targets - Tarragona, Spain
Duration: 27 Jun 20051 Jul 2005

Publication series

Name32nd EPS Conference on Plasma Physics 2005, EPS 2005, Held with the 8th International Workshop on Fast Ignition of Fusion Targets - Europhysics Conference Abstracts
Volume1

Conference

Conference32nd European Physical Society Conference on Plasma Physics and Controlled Fusion combined with the 8th International Workshop on Fast Ignition of Fusion Targets
Country/TerritorySpain
CityTarragona
Period27/06/051/07/05

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