DocumentCode :
2930882
Title :
Towards diagnostics for a fusion reactor
Author :
Costley, A.E.
Author_Institution :
Cadarache Centre, ITER Organ., St. Paul-lez-Durance, France
fYear :
2009
fDate :
7-10 June 2009
Firstpage :
1
Lastpage :
10
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 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 United States. 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 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 diagnostics techniques will differ. The challenges for DEMO diagnostics are substantial and a dedicated effort should be made to find and develop new techniques, and especially 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 reactor design; plasma diagnostics; plasma toroidal confinement; Cadarache; China; DEMO reactor; Europe; France; ITER; India; International Thermonuclear Experimental Reactor; JET; Japan; Korea; Russian Federation; United States; fusion reactor diagnostics; laser based optical system; magnetic confinement fusion; magnetics; neutron system; tokamak fusion plasma; vacuum vessel; Europe; Fusion reactors; Inductors; Laser fusion; Laser modes; Magnetic confinement; Neutrons; Plasma diagnostics; Plasma measurements; Tokamaks; DEMO; ITER; Plasma measurements; diagnostics;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2009 First International Conference on
Conference_Location :
Marseille
Print_ISBN :
978-1-4244-5207-1
Electronic_ISBN :
978-1-4244-5208-8
Type :
conf
DOI :
10.1109/ANIMMA.2009.5503733
Filename :
5503733
Link To Document :
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