Physics:Quantum Stellarator - Revision history

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	'''Stellarator''' is a class of [[Physics:Quantum Magnetic confinement fusion\|magnetic confinement fusion]] device that confines hot ~~[[Software:Plasma\|~~plasma]] almost entirely with externally generated magnetic fields. Unlike a ~~[[Software:Tokamak\|~~tokamak]], a stellarator does not rely on a large induced plasma current to create the rotational transform needed for confinement. This makes the stellarator intrinsically attractive for long-pulse or steady-state fusion operation, because it avoids many current-driven instabilities that complicate tokamak performance.<ref name="Spitzer1958">{{cite journal		'''Stellarator''' is a class of [[Physics:Quantum Magnetic confinement fusion\|magnetic confinement fusion]] device that confines hot plasma almost entirely with externally generated magnetic fields. Unlike a tokamak, a stellarator does not rely on a large induced plasma current to create the rotational transform needed for confinement. This makes the stellarator intrinsically attractive for long-pulse or steady-state fusion operation, because it avoids many current-driven instabilities that complicate tokamak performance.<ref name="Spitzer1958">{{cite journal
	\|last=Spitzer		\|last=Spitzer
	\|first=Lyman		\|first=Lyman
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	}}</ref>		}}</ref>

	The concept was invented by ~~[[Biography:~~Lyman Spitzer~~\|Lyman Spitzer]]~~ in 1951 at what became the ~~[[Organization:Princeton Plasma Physics Laboratory\|~~Princeton Plasma Physics Laboratory]] (PPPL). Early stellarators demonstrated the feasibility of magnetic confinement, but their transport losses were much larger than hoped. After the strong rise of the tokamak in the late 1960s, stellarator research declined in the United States, though it continued in Europe and Japan. Since the 1990s, advances in computation, coil design, and magnetic optimization have revived stellarators as serious reactor candidates, especially through devices such as ~~[[Physics:~~Wendelstein 7-X~~\|Wendelstein 7-X]]~~, the ~~[[Physics:~~Helically Symmetric Experiment~~\|Helically Symmetric Experiment]]~~ (HSX), and the ~~[[Physics:Large Helical Device\|~~Large Helical Device]] (LHD).<ref name="Stix1998">{{cite journal		The concept was invented by Lyman Spitzer in 1951 at what became the Princeton Plasma Physics Laboratory (PPPL). Early stellarators demonstrated the feasibility of magnetic confinement, but their transport losses were much larger than hoped. After the strong rise of the tokamak in the late 1960s, stellarator research declined in the United States, though it continued in Europe and Japan. Since the 1990s, advances in computation, coil design, and magnetic optimization have revived stellarators as serious reactor candidates, especially through devices such as Wendelstein 7-X, the Helically Symmetric Experiment (HSX), and the Large Helical Device (LHD).<ref name="Stix1998">{{cite journal
	\|last=Stix		\|last=Stix
	\|first=Thomas		\|first=Thomas
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	=== Origins ===		=== Origins ===
	The general fusion problem emerged from early nuclear reaction work in the 1930s, including the deuterium-fusion experiments of ~~[[Biography:~~Mark Oliphant~~\|Mark Oliphant]]~~, Paul Harteck, and ~~[[Biography:Ernest Rutherford\|~~Ernest Rutherford]]. These studies helped establish that thermonuclear fusion would require extremely high particle energies and therefore temperatures far beyond those tolerated by ordinary material walls.<ref name="Oliphant1934">{{cite journal		The general fusion problem emerged from early nuclear reaction work in the 1930s, including the deuterium-fusion experiments of Mark Oliphant, Paul Harteck, and Ernest Rutherford. These studies helped establish that thermonuclear fusion would require extremely high particle energies and therefore temperatures far beyond those tolerated by ordinary material walls.<ref name="Oliphant1934">{{cite journal
	\|journal=Nature		\|journal=Nature
	\|first1=Mark		\|first1=Mark
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	=== HSX and quasi-symmetry ===		=== HSX and quasi-symmetry ===
	A major milestone came from the ~~[[Physics:Helically Symmetric Experiment\|~~HSX]] at the University of Wisconsin, which demonstrated that quasi-helical symmetry can substantially reduce neoclassical transport. Experiments showed improved particle and heat confinement when the configuration was tuned toward quasi-symmetry compared with intentionally symmetry-broken cases.<ref name="Canik2007" />		A major milestone came from the HSX at the University of Wisconsin, which demonstrated that quasi-helical symmetry can substantially reduce neoclassical transport. Experiments showed improved particle and heat confinement when the configuration was tuned toward quasi-symmetry compared with intentionally symmetry-broken cases.<ref name="Canik2007" />

	=== Wendelstein 7-X ===		=== Wendelstein 7-X ===
	The most advanced optimized stellarator currently in operation is ~~[[Physics:~~Wendelstein 7-X~~\|Wendelstein 7-X]]~~ in Greifswald, Germany. W7-X was designed to test whether careful magnetic optimization can suppress neoclassical transport to reactor-relevant levels while supporting long-pulse operation.<ref name="Clery2015" /><ref name="Dinklage2018" />		The most advanced optimized stellarator currently in operation is Wendelstein 7-X in Greifswald, Germany. W7-X was designed to test whether careful magnetic optimization can suppress neoclassical transport to reactor-relevant levels while supporting long-pulse operation.<ref name="Clery2015" /><ref name="Dinklage2018" />

	Results from W7-X have shown reduced neoclassical energy transport, effective magnetic optimization, and strong control over bootstrap current, supporting the stellarator strategy of achieving confinement quality through three-dimensional field design rather than large plasma current.<ref name="Beidler2021" /><ref name="Dinklage2018" />		Results from W7-X have shown reduced neoclassical energy transport, effective magnetic optimization, and strong control over bootstrap current, supporting the stellarator strategy of achieving confinement quality through three-dimensional field design rather than large plasma current.<ref name="Beidler2021" /><ref name="Dinklage2018" />
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	=== Torsatron and heliotron ===		=== Torsatron and heliotron ===
	A torsatron uses continuous helical windings to generate the confining field. A heliotron is a closely related configuration, developed especially in Japan, that combines helical coils with additional poloidal-field coils. The ~~[[Physics:~~Large Helical Device~~\|Large Helical Device]]~~ is a leading heliotron example.<ref name="Johnson1982" /><ref name="Wakatani1998">{{cite book		A torsatron uses continuous helical windings to generate the confining field. A heliotron is a closely related configuration, developed especially in Japan, that combines helical coils with additional poloidal-field coils. The Large Helical Device is a leading heliotron example.<ref name="Johnson1982" /><ref name="Wakatani1998">{{cite book
	\|last=Wakatani		\|last=Wakatani
	\|first=M.		\|first=M.

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	{{Author\|Harold Foppele}}		{{Author\|Harold Foppele}}

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	'''Stellarator''' is a class of [[Physics:Quantum Magnetic confinement fusion\|magnetic confinement fusion]] device that confines hot [[Software:Plasma\|plasma]] almost entirely with externally generated magnetic fields. Unlike a [[Software:Tokamak\|tokamak]], a stellarator does not rely on a large induced plasma current to create the rotational transform needed for confinement. This makes the stellarator intrinsically attractive for long-pulse or steady-state fusion operation, because it avoids many current-driven instabilities that complicate tokamak performance.<ref name="Spitzer1958">{{cite journal		'''Stellarator''' is a class of [[Physics:Quantum Magnetic confinement fusion\|magnetic confinement fusion]] device that confines hot [[Software:Plasma\|plasma]] almost entirely with externally generated magnetic fields. Unlike a [[Software:Tokamak\|tokamak]], a stellarator does not rely on a large induced plasma current to create the rotational transform needed for confinement. This makes the stellarator intrinsically attractive for long-pulse or steady-state fusion operation, because it avoids many current-driven instabilities that complicate tokamak performance.<ref name="Spitzer1958">{{cite journal
	\|last=Spitzer		\|last=Spitzer
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	\|pmid=34381232		\|pmid=34381232
	}}</ref>		}}</ref>
	[[File:Magnetic field stellarator yellow.jpg\|thumb\|~~400px~~\|~~Schematic magnetic geometry of a stellarator, in which external coils generate rotational transform and confine plasma without requiring a large toroidal plasma current~~.]]		</div>

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			[[File:Magnetic field stellarator yellow.jpg\|thumb\|280px\|Quantum Stellarator.]]
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	== Historical development ==		== Historical development ==

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