Plasma-surface interactions during tokamak disruptions and rapid shutdowns

被引：40

作者：

Hollmann, E. M. ^{[1
]}

Arnoux, G. ^{[2
]}

Commaux, N. ^{[3
]}

Eidietis, N. W. ^{[4
]}

Evans, T. E. ^{[4
]}

Granetz, R. S. ^{[5
]}

Huber, A. ^{[7
]}

Humphreys, D. A. ^{[4
]}

Izzo, V. A. ^{[1
]}

James, A. N. ^{[1
]}

Jernigan, T. C. ^{[3
]}

Lehnen, M. ^{[7
]}

Maddaluno, G. ^{[8
]}

Paccagnella, R. ^{[9
]}

Parks, P. B. ^{[4
]}

Philipps, V. ^{[7
]}

Reinke, M. L. ^{[5
]}

Rudakov, D. L. ^{[1
]}

Saint-Laurent, F. ^{[10
]}

Sizyuk, V. ^{[6
]}

Strait, E. J. ^{[4
]}

Wesley, J. C. ^{[4
]}

Wong, C. P. C. ^{[4
]}

Yu, J. H. ^{[1
]}

机构：

[1] Univ Calif San Diego, La Jolla, CA 92093 USA

[2] JET EFDA, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England

[3] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA

[4] Gen Atom Co, San Diego, CA 92186 USA

[5] MIT Plasma Sci & Fus Ctr, Cambridge, MA 02139 USA

[6] Purdue Univ, W Lafayette, IN 47907 USA

[7] Forschungszentrum Julich GmbH, Inst Energieforsch Plasmaphys, D-52425 Julich, Germany

[8] Assoc EURATOM NAE Fus, Ctr Rice Frascati, I-00044 Rome, Italy

[9] Consorzio RFX, Assoc Euratom ENAE Fus, Padua, Italy

[10] CEA, IRFM, F-13108 St Paul Les Durance, France

来源：

JOURNAL OF NUCLEAR MATERIALS | 2011年 / 415卷 / 01期

关键词：

TRANSIENT HEAT LOADS; RUNAWAY ELECTRONS; DIII-D; POWER LOAD; ITER; EROSION; JET; MITIGATION; IMPURITY; ARMOR;

D O I：

10.1016/j.jnucmat.2010.10.009

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Recent progress in understanding of disruptions and in developing methods to avoid disruption damage is presented. Nearly complete mitigation of conducted heat loads has been achieved with high-Z gas jet shutdown. The resulting local radiation heat flash melting in the main chamber might be a concern in ITER, especially with beryllium walls. During the current quench, significant vessel forces can occur due to halo currents I-halo; however, these are found to fall reliably below a boundary of (halo current fraction times halo current peaking factor) <0.7 both experimentally and numerically. Numerical simulations indicate that runaway electrons (REs) could cause serious damage to hard-to reach components in ITER, making their suppression a high priority. During the current quench, less than 20% of the density required for collisional suppression of REs appears to have been achieved. Collisional suppression of REs may have been achieved, however, in full-current RE beams with gas injection. (C) 2010 Elsevier B.V. All rights reserved.

引用

页码：S27 / S34

页数：8

共 62 条

[1] First measurements of main chamber power load during JET disruptions [J].