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ITER (initially the International Thermonuclear Experimental Reactor, iter meaning "the way" or "the path" in Latin [2] [3] [4]) is an international nuclear fusion research and engineering megaproject aimed at creating energy through a fusion process similar to that of the Sun. It is being built next to the Cadarache facility in southern France.
The ITER tokamak experiment under construction, which aims to demonstrate scientific breakeven, will be the world's largest MCF device. While early stellarators of low confinement in the 1950s were overshadowed by the initial success of tokamaks, interests in stellarators re-emerged attributing to their inherent capability for steady-state and ...
[8] [9] However, the ITER experience suggests that development of a multi-billion US dollar tokamak-based technology innovation cycle able to develop fusion power stations that can compete with non-fusion energy technologies is likely to encounter the "valley of death" problem in venture capital, i.e., insufficient investment to go beyond ...
Neutron flux causes reactor vessels to suffer from neutron embrittlement and is a major problem with thermonuclear fusion like ITER and other magnetic confinement D-T reactors where fast (originally 14.06 MeV) neutrons damage equipment resulting in short equipment lifetime and huge costs and large volumes of radioactive waste streams.
Similar problems were seen in all the contemporary designs, for one reason or another. The stellarator, various pinch concepts and the magnetic mirror machines in both the US and USSR all demonstrated problems that limited their confinement times. [52] From the first studies of controlled fusion, there was a problem lurking in the background.
To deliver power to the fusion plasma in ITER, two heating neutral beam injectors will be installed. They are designed to provide the power of 17 MW each, through the 23 m beamlines, up to the four-meter diameter container: in order to deposit sufficient heating power in the plasma core instead of the plasma edges, the beam particle energy shall be about 1 MeV, thus increasing the neutral beam ...
ASDEX Upgrade will examine ways to overcome this problem, in preparation for the construction of ITER's first wall. The experiment has an overall radius of 5 metres, a gross weight of 800 metric tons , a maximum magnetic field strength of 3.1 tesla , a maximum plasma current of 1.6 megaampere and maximum heating power of up to 27 megawatt .
KSTAR is one of the first research tokamaks in the world to feature fully superconducting magnets, which again will be of great relevance to ITER as this will also use superconducting magnets. The KSTAR magnet system consists of 16 niobium – tin direct current toroidal field magnets, 10 niobium – tin alternating current poloidal field ...