DocumentCode :
1311203
Title :
Towards Diagnostics for a Fusion Reactor
Author :
Costley, Alan E.
Author_Institution :
Culham Centre for Fusion Energy, Abingdon, UK
Volume :
38
Issue :
10
fYear :
2010
Firstpage :
2934
Lastpage :
2943
Abstract :
The requirements for measurements on modern tokamak fusion plasmas are outlined, and the techniques and systems used to make the measurements, usually referred to as “diagnostics”, are introduced. The basics of three particular diagnostics - magnetics, neutron systems, and a laser based optical system - are outlined as examples of modern diagnostic systems, and the implementation of these diagnostics on a current tokamak (JET) are described. The next major step in magnetic confinement fusion (MCF) is the construction and operation of the International Thermonuclear Experimental Reactor (ITER), which is a joint project of China, Europe, Japan, India, Korea, the Russian Federation, and the U.S. Construction has begun in Cadarache, France. It is expected that ITER will operate at the 500 MW level. Because of the harsh environment in the vacuum vessel where many diagnostic components are located, the development of diagnostics for ITER is a major challenge - arguably the most difficult challenge ever undertaken in the field of MCF diagnostics. The main elements in the diagnostic step are outlined using the three chosen techniques as examples. Finally, the step beyond ITER to a demonstration reactor, DEMO, that is expected to produce several GWs of fusion power is considered and the impact on diagnostics outlined. It is shown that the applicability and development steps needed for the individual diagnostic techniques will differ. The challenges for DEMO diagnostics are substantial and a dedicated effort is required to find and develop new techniques, and special techniques appropriate to the DEMO environment. It is argued that the limitations and difficulties in diagnostics should be a consideration in the optimization and designs of candidate DEMOs.
Keywords :
Tokamak devices; fusion reactors; plasma diagnostics; plasma toroidal confinement; ITER; International Thermonuclear Experimental Reactor; JET; fusion reactor; laser-based optical system; magnetic confinement fusion; magnetics diagnostics; neutron systems; optimization; plasma diagnostics; power 500 MW; tokamak fusion plasmas; vacuum vessel; Atmospheric measurements; Neutrons; Particle measurements; Plasma measurements; Plasmas; Temperature measurement; Toroidal magnetic fields; DEMO; fusion reactors; international thermonuclear experimental reactor (ITER); plasma diagnostics; plasma measurements;
fLanguage :
English
Journal_Title :
Plasma Science, IEEE Transactions on
Publisher :
ieee
ISSN :
0093-3813
Type :
jour
DOI :
10.1109/TPS.2010.2064182
Filename :
5560872
Link To Document :
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