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  2. Toroidal solenoid - Wikipedia

    en.wikipedia.org/wiki/Toroidal_solenoid

    The toroidal solenoid was an early 1946 design for a fusion power device designed by George Paget Thomson and Moses Blackman of Imperial College London.It proposed to confine a deuterium fuel plasma to a toroidal (donut-shaped) chamber using magnets, and then heating it to fusion temperatures using radio frequency energy in the fashion of a microwave oven.

  3. National Spherical Torus Experiment - Wikipedia

    en.wikipedia.org/wiki/National_Spherical_Torus...

    It doubles the toroidal field (to 1 Tesla), plasma current (to 2 MA) and heating power. It increases the pulse duration by a factor of five. [3] To achieve this the central stack (CS) solenoid was widened, [4] and an OH coil, inner poloidal coils, and a 2nd neutral-ion beam line were added. [5]

  4. Spherical tokamak - Wikipedia

    en.wikipedia.org/wiki/Spherical_tokamak

    However, the difference in that field is a function of aspect ratio; an infinitely large toroid would approximate a straight solenoid, while an ST maximizes the difference in field strength. Moreover, as there are certain aspects of reactor design that are fixed in size, the aspect ratio might be forced into certain configurations.

  5. Froebel gifts - Wikipedia

    en.wikipedia.org/wiki/Froebel_gifts

    Joachim Liebschner commented in his book, A Child's Work: Freedom and Guidance in Froebel's Educational Theory and Practice "Realising how the Gifts were eventually misused by Kindergarten teachers who followed after Fröbel, it is important to consider what Fröbel expected the gifts to achieve. He envisaged that the Gifts will teach the child ...

  6. Safety factor (plasma physics) - Wikipedia

    en.wikipedia.org/wiki/Safety_factor_(plasma_physics)

    In a toroidal fusion power reactor, the magnetic fields confining the plasma are formed in a helical shape, winding around the interior of the reactor. The safety factor, labeled q or q(r), is the ratio of the times a particular magnetic field line travels around a toroidal confinement area's "long way" (toroidally) to the "short way" (poloidally).

  7. Pegasus Toroidal Experiment - Wikipedia

    en.wikipedia.org/wiki/Pegasus_Toroidal_Experiment

    The Pegasus Toroidal Experiment is a plasma confinement experiment relevant to fusion power production, run by the Department of Engineering Physics of the University of Wisconsin–Madison. It is a spherical tokamak , a very low-aspect-ratio version of the tokamak configuration, i.e. the minor radius of the torus is comparable to the major radius.

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