Chapter 7: Diagnostics

被引：349

作者：

FOM-Institute for Plasma Physics Rijnhuizen, Association EURATOM-FOM, Partner in the Trilateral Euregio Cluster, PO Box 1207, 3430 BE Nieuwegein, Netherlands ^{[1
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机构：

[1] FOM-Institute for Plasma Physics Rijnhuizen, Association EURATOM-FOM, Partner in the Trilateral Euregio Cluster, 3430 BE Nieuwegein

[2] ITER Cadarache JWS, Cadarache Centre

[3] EURATOM-Risø National Laboratory

[4] General Atomics, San Diego

[5] Max-Planck-Institute for Plasma Physics, D-85748 Garching

[6] European Commission, Directorate-General for Research, B-1050 Bruxelles

[7] Max-Planck-Institute for Plasma Physics, 17491 Greifswald, Wendelsteinstrasse

[8] Laboratorio Nacional de Fusión, EURATOM-CIEMAT

[9] EFDA CSU Garching, D-85748 Garching

[10] Japan Atomic Energy Agency, Naka, Ibaraki-ken

[11] Princeton Plasma Physics Laboratory, Princeton

[12] SRC RF TRINITI, Troitsk

[13] Institut für Plasmaphysik, Forschungszentrum Jülich GmbH, Partner in the Trilateral Euregio Cluster

[14] Association Euratom-CEA, DSM/DRFC, CEN Cadarache

[15] Consorzio RFX, Associazione EURATOM-ENEA sulla Fusione, Padova

[16] ENEA, 00044 Frascati

[17] National Institute for Fusion Science (NIFS), Toki, Gifu 509-5292

[18] Ioffe Physico-Technical Institute, St Petersburg

[19] Department of Quantum Science and Energy Engineering, Tohoku University

[20] Institute of Plasma Physics, NSC Kharkov Institute of Physics and Technology

[21] Nuclear Fusion Institute, RRC 'Kurchatov Institute'

来源：

Nucl Fusion | 2007年 / 6卷 / S337-S384期

关键词：

Tokamak devices;

D O I：

10.1088/0029-5515/47/6/S07

中图分类号：

学科分类号：

摘要：

In order to support the operation of ITER and the planned experimental programme an extensive set of plasma and first wall measurements will be required. The number and type of required measurements will be similar to those made on the present-day large tokamaks while the specification of the measurements - time and spatial resolutions, etc - will in some cases be more stringent. Many of the measurements will be used in the real time control of the plasma driving a requirement for very high reliability in the systems (diagnostics) that provide the measurements. The implementation of diagnostic systems on ITER is a substantial challenge. Because of the harsh environment (high levels of neutron and gamma fluxes, neutron heating, particle bombardment) diagnostic system selection and design has to cope with a range of phenomena not previously encountered in diagnostic design. Extensive design and R&D is needed to prepare the systems. In some cases the environmental difficulties are so severe that new diagnostic techniques are required. The starting point in the development of diagnostics for ITER is to define the measurement requirements and develop their justification. It is necessary to include all the plasma parameters needed to support the basic and advanced operation (including active control) of the device, machine protection and also those needed to support the physics programme. Once the requirements are defined, the appropriate (combination of) diagnostic techniques can be selected and their implementation onto the tokamak can be developed. The selected list of diagnostics is an important guideline for identifying dedicated research and development needs in the area of ITER diagnostics. This paper gives a comprehensive overview of recent progress in the field of ITER diagnostics with emphasis on the implementation issues. After a discussion of the measurement requirements for plasma parameters in ITER and their justifications, recent progress in the field of diagnostics to measure a selected set of plasma parameters is presented. The integration of the various diagnostic systems onto the ITER tokamak is described. Generic research and development in the field of irradiation effects on materials and environmental effects on first mirrors are briefly presented. The paper ends with an assessment of the measurement capability for ITER and a forward of what will be gained from operation of the various diagnostic systems on ITER in preparation for the machines that will follow ITER. © 2007 IAEA, Vienna.

引用

页码：S337 / S384

页数：47

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