Disruptions in ITER and strategies for their control and mitigation

被引：323

作者：

Lehnen, M. ^{[1
]}

Aleynikova, K. ^{[1
]}

Aleynikov, P. B. ^{[1
]}

Campbell, D. J. ^{[1
]}

Drewelow, P. ^{[2
]}

Eidietis, N. W. ^{[3
]}

Gasparyan, Yu. ^{[4
]}

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

Gribov, Y. ^{[1
]}

Hartmann, N. ^{[6
]}

Hollmann, E. M. ^{[7
]}

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

Jachmich, S. ^{[8
]}

Kim, S. -H. ^{[1
]}

Kocan, M. ^{[1
]}

Koslowski, H. R. ^{[6
]}

Kovalenko, D. ^{[9
]}

Kruezi, U. ^{[10
]}

Loarte, A. ^{[1
]}

Maruyama, S. ^{[1
]}

Matthews, G. F. ^{[10
]}

Parks, P. B. ^{[3
]}

Pautasso, G. ^{[11
]}

Pitts, R. A. ^{[1
]}

Reux, C. ^{[12
]}

Riccardo, V. ^{[10
]}

Roccella, R. ^{[1
]}

Snipes, J. A. ^{[1
]}

Thornton, A. J. ^{[10
]}

de Vries, P. C. ^{[1
]}

机构：

[1] ITER Org, F-13115 St Paul Les Durance, France

[2] EURATOM Ass, Greifswald Branch, Max Planck Inst Plasmaphys, D-17491 Greifswald, Germany

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

[4] Natl Res Nucl Univ MEPhI, Moscow Engn Phys Inst, Moscow 115409, Russia

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

[6] Forschungszentrum Julich, Inst Energy & Climate Res Plasma Phys, Assoc EURATOM FZJ, Trilateral Euregio Cluster, D-52425 Julich, Germany

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

[8] Assoc EURATOM Belgian State, Plasma Phys Lab, ERM KMS, B-1000 Brussels, Belgium

[9] SRC RF TRINITI, Moscow 142190, Russia

[10] Culham Sci Ctr, CCFE, Abingdon OX14 3DB, Oxon, England

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

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

来源：

JOURNAL OF NUCLEAR MATERIALS | 2015年 / 463卷

基金：

欧盟地平线“2020”;

关键词：

RUNAWAY CURRENT TERMINATION; PLASMA-FACING COMPONENTS; HEAT LOADS; IMPURITY; TOKAMAK; JET; ELECTRONS; SHUTDOWN;

D O I：

10.1016/j.jnucmat.2014.10.075

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

The thermal and electromagnetic loads related to disruptions in ITER are substantial and require careful design of tokamak components to ensure they reach the projected lifetime and to ensure that safety relevant components fulfil their function for the worst foreseen scenarios. The disruption load specifications are the basis for the design process of components like the full-W diverton the blanket modules and the vacuum vessel and will set the boundary conditions for ITER operations. This paper will give a brief overview on the disruption loads and mitigation strategies for ITER and will discuss the physics basis which is continuously refined through the current disruption R&D programs. (C) 2014 ITER Organization. Published by Elsevier B.V. All rights reserved.

引用

页码：39 / 48

页数：10

共 65 条

[61] Study of discharge quenching in the T-10 tokamak by injecting high-Z impurity pellets [J].