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** A '''tokamak ''' () is a device which uses a powerful [[magnetic field]] to confine a hot [[plasma (physics)|plasma]] in the shape of a [[torus]]. The tokamak is one of several types of [[magnetic confinement fusion|magnetic confinement devices]] being developed to produce controlled [[thermonuclear]] [[fusion power]]. , it is the leading candidate for a practical [[fusion reactor]].<ref name="Greenwald2016"></ref> <P> Tokamaks were initially conceptualized in the 1950s by [[List of Russian physicists|Soviet physicists]] [[Igor Yevgenyevich Tamm|Igor Tamm]] and [[Andrei Sakharov]], inspired by a letter by [[Oleg Lavrentiev]]. Meanwhile, the first working tokamak was attributed to the work of [[Natan Yavlinsky|Natan Yavlinskii]] on the T-1.<ref name=autogenerated1></ref> It had been demonstrated that a [[plasma equilibria and stability|stable plasma equilibrium]] requires [[magnetic field#Magnetic field lines|magnetic field lines]] that wind around the torus in a [[helix]]. Devices like the [[z-pinch]] and [[stellarator]] had attempted this, but demonstrated serious instabilities. It was the development of the concept now known as the [[Safety factor (plasma physics)|safety factor]] (labelled ''q'' in mathematical notation) that guided tokamak development; by arranging the reactor so this critical factor ''q'' was always greater than 1, the tokamaks strongly suppressed the instabilities which plagued earlier designs. <P> The first tokamak, the T-1, began operation in 1958. By the mid-1960s, the tokamak designs began to show greatly improved performance. Initial results were released in 1965, but were ignored; [[Lyman Spitzer]] dismissed them out of hand after noting potential problems in their system for measuring temperatures. A second set of results was published in 1968, this time claiming performance far in advance of any other machine, and was likewise considered unreliable. This led to the invitation of a delegation from the [[United Kingdom]] to make their own measurements. These confirmed the Soviet results, and their 1969 publication resulted in a stampede of tokamak construction. <P> By the mid-1970s, dozens of tokamaks were in use around the world. By the late 1970s, these machines had reached all of the conditions needed for practical fusion, although not at the same time nor in a single reactor. With the goal of [[Fusion energy gain factor|breakeven]] now in sight, a new series of machines were designed that would run on a fusion fuel of [[deuterium]] and [[tritium]]. These machines, notably the [[Joint European Torus]] (JET), [[Tokamak Fusion Test Reactor]] (TFTR) and [[JT-60]], had the explicit goal of reaching breakeven. <P> Instead, these machines demonstrated new problems that limited their performance. Solving these would require a much larger and more expensive machine, beyond the abilities of any one country. After an initial agreement between [[Ronald Reagan]] and [[Mikhail Gorbachev]] in November 1985, the [[International Thermonuclear Experimental Reactor]] (ITER) effort emerged and remains the primary international effort to develop practical fusion power. Many smaller designs, and offshoots like the [[spherical tokamak]], continue to be used to investigate performance parameters and other issues. , JET remains the record holder for fusion output, reaching 16&nbsp;MW of output for 24&nbsp;MW of input heating power.
** A '''tokamak ''' () is a device which uses a powerful [[magnetic field]] to confine a hot [[plasma (physics)|plasma]] in the shape of a [[torus]]. The tokamak is one of several types of [[magnetic confinement fusion|magnetic confinement devices]] being developed to produce controlled [[thermonuclear]] [[fusion power]]. , it is the leading candidate for a practical [[fusion reactor]].<ref name="Greenwald2016"></ref> <P> Tokamaks were initially conceptualized in the 1950s by [[List of Russian physicists|Soviet physicists]] [[Igor Yevgenyevich Tamm|Igor Tamm]] and [[Andrei Sakharov]], inspired by a letter by [[Oleg Lavrentiev]]. Meanwhile, the first working tokamak was attributed to the work of [[Natan Yavlinsky|Natan Yavlinskii]] on the T-1.<ref name=autogenerated1></ref> It had been demonstrated that a [[plasma equilibria and stability|stable plasma equilibrium]] requires [[magnetic field#Magnetic field lines|magnetic field lines]] that wind around the torus in a [[helix]]. Devices like the [[z-pinch]] and [[stellarator]] had attempted this, but demonstrated serious instabilities. It was the development of the concept now known as the [[Safety factor (plasma physics)|safety factor]] (labelled ''q'' in mathematical notation) that guided tokamak development; by arranging the reactor so this critical factor ''q'' was always greater than 1, the tokamaks strongly suppressed the instabilities which plagued earlier designs. <P> The first tokamak, the T-1, began operation in 1958. By the mid-1960s, the tokamak designs began to show greatly improved performance. Initial results were released in 1965, but were ignored; [[Lyman Spitzer]] dismissed them out of hand after noting potential problems in their system for measuring temperatures. A second set of results was published in 1968, this time claiming performance far in advance of any other machine, and was likewise considered unreliable. This led to the invitation of a delegation from the [[United Kingdom]] to make their own measurements. These confirmed the Soviet results, and their 1969 publication resulted in a stampede of tokamak construction. <P> By the mid-1970s, dozens of tokamaks were in use around the world. By the late 1970s, these machines had reached all of the conditions needed for practical fusion, although not at the same time nor in a single reactor. With the goal of [[Fusion energy gain factor|breakeven]] now in sight, a new series of machines were designed that would run on a fusion fuel of [[deuterium]] and [[tritium]]. These machines, notably the [[Joint European Torus]] (JET), [[Tokamak Fusion Test Reactor]] (TFTR) and [[JT-60]], had the explicit goal of reaching breakeven. <P> Instead, these machines demonstrated new problems that limited their performance. Solving these would require a much larger and more expensive machine, beyond the abilities of any one country. After an initial agreement between [[Ronald Reagan]] and [[Mikhail Gorbachev]] in November 1985, the [[International Thermonuclear Experimental Reactor]] (ITER) effort emerged and remains the primary international effort to develop practical fusion power. Many smaller designs, and offshoots like the [[spherical tokamak]], continue to be used to investigate performance parameters and other issues. , JET remains the record holder for fusion output, reaching 16&nbsp;MW of output for 24&nbsp;MW of input heating power.
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=== 2020 ===
* ...
** QUOTE: ... In a [[tokamak]], fusion power is determined by temperature, plasma density and confinement time. Fusion gain, expressed as the symbol Q, is the ratio of fusion power to the input power required to maintain the reaction and is thus a key indicator of the device's efficiency. At Q = 1, the breakeven point has been reached, but because of heat losses, self-sustaining plasmas are not reached until about Q = 5. Current systems have achieved extrapolated values of Q = 1.2. The ITER experiment under construction in France is expected to achieve Q = 10, but commercial fusion power plants will likely need to achieve even higher Q values to be economical.


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Revision as of 15:37, 22 May 2020

A Tokamak Reactor is a fusion reactor that ...



References

2020

  • (Wikipedia, 2020) ⇒ https://en.wikipedia.org/wiki/Tokamak Retrieved:2020-5-22.
    • A tokamak () is a device which uses a powerful magnetic field to confine a hot plasma in the shape of a torus. The tokamak is one of several types of magnetic confinement devices being developed to produce controlled thermonuclear fusion power. , it is the leading candidate for a practical fusion reactor.[1]

      Tokamaks were initially conceptualized in the 1950s by Soviet physicists Igor Tamm and Andrei Sakharov, inspired by a letter by Oleg Lavrentiev. Meanwhile, the first working tokamak was attributed to the work of Natan Yavlinskii on the T-1.[2] It had been demonstrated that a stable plasma equilibrium requires magnetic field lines that wind around the torus in a helix. Devices like the z-pinch and stellarator had attempted this, but demonstrated serious instabilities. It was the development of the concept now known as the safety factor (labelled q in mathematical notation) that guided tokamak development; by arranging the reactor so this critical factor q was always greater than 1, the tokamaks strongly suppressed the instabilities which plagued earlier designs.

      The first tokamak, the T-1, began operation in 1958. By the mid-1960s, the tokamak designs began to show greatly improved performance. Initial results were released in 1965, but were ignored; Lyman Spitzer dismissed them out of hand after noting potential problems in their system for measuring temperatures. A second set of results was published in 1968, this time claiming performance far in advance of any other machine, and was likewise considered unreliable. This led to the invitation of a delegation from the United Kingdom to make their own measurements. These confirmed the Soviet results, and their 1969 publication resulted in a stampede of tokamak construction.

      By the mid-1970s, dozens of tokamaks were in use around the world. By the late 1970s, these machines had reached all of the conditions needed for practical fusion, although not at the same time nor in a single reactor. With the goal of breakeven now in sight, a new series of machines were designed that would run on a fusion fuel of deuterium and tritium. These machines, notably the Joint European Torus (JET), Tokamak Fusion Test Reactor (TFTR) and JT-60, had the explicit goal of reaching breakeven.

      Instead, these machines demonstrated new problems that limited their performance. Solving these would require a much larger and more expensive machine, beyond the abilities of any one country. After an initial agreement between Ronald Reagan and Mikhail Gorbachev in November 1985, the International Thermonuclear Experimental Reactor (ITER) effort emerged and remains the primary international effort to develop practical fusion power. Many smaller designs, and offshoots like the spherical tokamak, continue to be used to investigate performance parameters and other issues. , JET remains the record holder for fusion output, reaching 16 MW of output for 24 MW of input heating power.

  1. Cite error: Invalid <ref> tag; no text was provided for refs named Greenwald2016
  2. Cite error: Invalid <ref> tag; no text was provided for refs named autogenerated1

2020

  • ...
    • QUOTE: ... In a tokamak, fusion power is determined by temperature, plasma density and confinement time. Fusion gain, expressed as the symbol Q, is the ratio of fusion power to the input power required to maintain the reaction and is thus a key indicator of the device's efficiency. At Q = 1, the breakeven point has been reached, but because of heat losses, self-sustaining plasmas are not reached until about Q = 5. Current systems have achieved extrapolated values of Q = 1.2. The ITER experiment under construction in France is expected to achieve Q = 10, but commercial fusion power plants will likely need to achieve even higher Q values to be economical.