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

被引：18

作者：

Kirschner, A. ^{[1
]}

Ohya, K. ^{[2
]}

Borodin, D. ^{[1
]}

Ding, R. ^{[1
,3
]}

Matveev, D. ^{[1
,4
]}

Philipps, V. ^{[1
]}

Samm, U. ^{[1
]}

机构：

[1] Forschungszentrum Julich, Assoc EURATOM FZJ, Inst Energieforsch Plasmaphys, Trilateral Euregio Cluster, D-52425 Julich, Germany

[2] Univ Tokushima, Inst Sci & Technol, Tokushima 7708506, Japan

[3] Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China

[4] Univ Ghent, Dept Appl Phys, B-9000 Ghent, Belgium

来源：

PHYSICA SCRIPTA | 2009年 / T138卷

关键词：

EROSION; CARBON; TRANSPORT; CODE;

D O I：

10.1088/0031-8949/2009/T138/014011

中图分类号：

O4 [物理学];

学科分类号：

0702 ;

摘要：

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.

引用

页数：6

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