Prediction of long-term tritium retention in the divertor of ITER: Influence of modelling assumptions on retention rates

A. Kirschner, K. Ohya, D. Borodin, R. Ding, D. Matveev, V. Philipps, U. Samm

Research output: Contribution to journalConference articlepeer-review

18 Scopus citations

Abstract

ERO modelling of long-term tritium (T) retention has been done for the divertor of ITER with graphite target plates assuming a certain beryllium influx into the divertor, eroded from the main chamber. The divertor beryllium (Be) influx relative to the deuterium ion flux has been fixed at 0.1% for the outer divertor and 1.0% for the inner divertor. In addition to the original B2-Eirene plasma background, the influence of variations of temperature and density in the divertor has been studied. Moreover, assumptions for enhanced erosion of redeposited carbon and effective sticking for hydrocarbons have been analysed. With graphite target plates, long-term tritium retention is dominated by T co-deposition in deposits. Within the studied parameter range, the modelling yields 200-500 possible ITER discharges without cleaning before reaching the safety limit of 700 g of in-vessel retained tritium. Surface temperature-dependent tritium amounts in carbon and beryllium deposits have been taken into account.

Original languageEnglish
Article number14011
JournalPhysica Scripta
VolumeT138
DOIs
StatePublished - 2009
Externally publishedYes
Event12th International Workshop on Plasma-Facing Materials and Components for Fusion Applications, PFMC-12 - Julich, Germany
Duration: 11 May 200914 May 2009

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