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[13] The term "tokamak" was coined in 1957 [14] by Igor Golovin, a student of academician Igor Kurchatov.It originally sounded like "tokamag" ("токамаг") — an acronym of the words "toroidal chamber magnetic" ("тороидальная камера магнитная"), but Natan Yavlinsky, the author of the first toroidal system, proposed replacing "-mag" with "-mak" for euphony. [15]
Prototype for development of Commercial Fusion Reactors 1.5–2 GW Fusion output. [63] K-DEMO (Korean fusion demonstration tokamak reactor) [64] Planned: 2037? National Fusion Research Institute: 6.8 m / 2.1 m: 7 T: 12 MA ? Prototype for the development of commercial fusion reactors with around 2200 MW of fusion power: DEMO (DEMOnstration Power ...
One of the ongoing research issues for commercial fusion power development is the choice of material for the plasma-facing portions of the reactor vessel, also known as the first wall. Most reactors operate at the equivalent of a high vacuum and thus demand high-strength materials to resists the inward pressure of the magnets against the empty ...
In other words, if the homogenous deuterium fuel was theoretically replaced with a 1:1 mix of deuterium and tritium, the fusion reaction would have created an energy output 1.05 times the energy used to start the reaction. JT-60U was not equipped to utilize tritium, as it would add extensive costs and safety risks.
For instance, production reactors would use a thick "blanket" containing lithium around the reactor core in order to capture the high-energy neutrons being released, both to protect the rest of the reactor mass from these neutrons as well as produce tritium for fuel. The size of the blanket is a function of the neutron's energy, which is 14 MeV ...
The tritium breeding blanket (also known as a fusion blanket, lithium blanket or simply blanket), is a key part of many proposed fusion reactor designs. It serves several purposes; primarily it is to produce (or "breed") further tritium fuel for the nuclear fusion reaction, which owing to the scarcity of tritium would not be available in sufficient quantities, through the reaction of neutrons ...
Later the intended location was at Troitsk near Moscow. [2] Ignitor was designed to produce approximately 100 MW of fusion power despite its relatively small size. For comparison, the intended weight was 500 metric tons, while the ITER international reactor, expected to be the first tokamak to reach scientific breakeven, is some 19,000 tons.
The Experimental Advanced Superconducting Tokamak (EAST), also known as HT-7U (Hefei Tokamak 7 Upgrade), is an experimental superconducting tokamak magnetic fusion energy reactor in Hefei, China. Operated by the Hefei Institutes of Physical Science conducting its experiments for the Chinese Academy of Sciences, EAST began its operations in 2006.