Estimations of erosion fluxes, material deposition and tritium retention in the divertor of ITER

被引：32

作者：

Kirschner, A. ^{[1
]}

Borodin, D. ^{[1
]}

Philipps, V. ^{[1
]}

Samm, U. ^{[1
]}

Ding, R. ^{[1
]}

Schmid, K. ^{[2
]}

Roth, J. ^{[2
]}

Kukushkin, A. ^{[3
]}

Federici, G. ^{[3
]}

Loarte, A. ^{[4
]}

机构：

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

[2] EURATOM, Max Planck Inst Plasmaphys, D-85748 Garching, Germany

[3] ITER JWS Garching Co Ctr, D-85748 Garching, Germany

[4] European Fus Dev Agreement, Close Support Unit, D-85748 Garching, Germany

来源：

JOURNAL OF NUCLEAR MATERIALS | 2009年 / 390-91卷

关键词：

CODE; SIMULATION; ISSUES; CARBON;

D O I：

10.1016/j.jnucmat.2009.01.155

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Material mixing effects on erosion/deposition and tritium retention in ITER have been modelled with ERO. It is seen that target lifetime is much less critical than tritium retention. A long-term tritium retention rate of similar to 9 mg T/s is obtained, assuming constant beryllium concentration in the background plasma of 0.1% for outer and 1 % for inner divertor. Retention in inner is about twice that in outer divertor. Using a TriDyn-based model for mixed layers instead of homogenous material mixing does change the detailed profiles of erosion and redeposition. However, overall tritium retention is almost unchanged. Also, profiles for the beryllium influx along the divertor plates calculated with Divlmp have been used for the ERO modelling. The resulting beryllium flux on the targets decreases by factors of 25 (inner) and 55 (outer divertor) compared to constant concentrations used so far. First ERO calculations using these beryllium profiles indicate a reduction of overall tritium retention by a factor of similar to 4 (compared to constant beryllium concentrations as used before), mainly due to reduced beryllium deposition. (C) 2009 Elsevier B.V. All rights reserved.

引用

页码：152 / 155

页数：4

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