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The Joint European Torus (JET) was a magnetically confined plasma physics experiment, located at Culham Centre for Fusion Energy in Oxfordshire, UK.Based on a tokamak design, the fusion research facility was a joint European project with the main purpose of opening the way to future nuclear fusion grid energy.
With better conditions for fusion in the plasma, the reactor performance increases. [23] Initial use of lithium in 1990s was motivated by a need for a low-recycling PFC. In 1996, ~ 0.02 grams of lithium coating was added to the PFC of TFTR, resulting in the fusion power output and the fusion plasma confinement to improve by a factor of two.
[45] [46] In 1974 J.B. Taylor re-visited ZETA and noticed that after an experimental run ended, the plasma entered a short period of stability. This led to the reversed field pinch concept. On May 1, 1974, the KMS fusion company (founded by Kip Siegel) achieved the world's first laser induced fusion in a deuterium-tritium pellet. [47]
DIII-D is a tokamak that has been operated since the late 1980s by General Atomics (GA) in San Diego, California, for the United States Department of Energy.The DIII-D National Fusion Facility is part of the ongoing effort to achieve magnetically confined fusion.
No fusion reactors had created a burning plasma until the competing NIF fusion project reached the milestone on 8 August 2021 using inertial confinement. [53] [54] At higher Q values, progressively bigger parts of plasma heating power will be produced by fusion reactions. [55] This reduces the power needed from external heating systems at high ...
A NIF fusion shot on September 27, 2013, produced more energy than was absorbed by the deuterium–tritium fuel. [120] This has been confused with having reached "scientific breakeven", [121] [122] defined as the fusion energy exceeding the laser input energy. [123] Using this definition gives 14.4 kJ out and 1.8 MJ in, a ratio of 0.008. [120]
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This was initially part of the stellarator designs, where it is easy to integrate into the magnetic windings. However, designing a divertor for a tokamak proved to be a very difficult design problem. Another problem seen in all fusion designs is the heat load that the plasma places on the wall of the confinement vessel.