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		<id>http://wiki.fusenet.eu/fusionwiki/index.php?title=Rotational_transform&amp;diff=7264</id>
		<title>Rotational transform</title>
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		<updated>2022-03-03T20:31:34Z</updated>

		<summary type="html">&lt;p&gt;Odstrcilt: Wrong definition of q95, it is 95% of poloidal flux (J. Wesson,  Tokamaks pg. 411)&lt;/p&gt;
&lt;hr /&gt;
&lt;div&gt;The rotational transform (or field line pitch) &#039;&#039;&amp;amp;iota;/2&amp;amp;pi;&#039;&#039; is defined as the number of poloidal transits per single toroidal transit of a field line on a toroidal flux surface.&lt;br /&gt;
The definition can be relaxed somewhat to include field lines moving in a spatial volume between two nested toroidal surfaces (e.g., a stochastic field region).&lt;br /&gt;
&lt;br /&gt;
Assuming the existence of toroidally nested magnetic [[Flux surface|flux surfaces]], the rotational transform on such a surface may also be  defined as&lt;br /&gt;
&amp;lt;ref&amp;gt;[http://link.aps.org/doi/10.1103/RevModPhys.76.1071 A.H. Boozer, &#039;&#039;Physics of magnetically confined plasmas&#039;&#039;, Rev. Mod. Phys. &#039;&#039;&#039;76&#039;&#039;&#039; (2004) 1071]&amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
:&amp;lt;math&amp;gt;\frac{\iota}{2 \pi} = \frac{d \psi}{d \Phi}&amp;lt;/math&amp;gt;&lt;br /&gt;
&lt;br /&gt;
where &#039;&#039;&amp;amp;psi;&#039;&#039; is the poloidal magnetic flux, and &amp;amp;Phi; the toroidal magnetic flux.&lt;br /&gt;
&lt;br /&gt;
== Safety factor ==&lt;br /&gt;
&lt;br /&gt;
In [[Tokamak|tokamak]] research, the quantity &#039;&#039;q = 2&amp;amp;pi;/&amp;amp;iota;&#039;&#039; is preferred (called the &amp;quot;safety factor&amp;quot;).&lt;br /&gt;
In a circular tokamak, &lt;br /&gt;
the equations of a field line on the flux surface are, approximately:&lt;br /&gt;
&amp;lt;ref&amp;gt;K. Miyamoto, &#039;&#039;Plasma Physics and Controlled Nuclear Fusion&#039;&#039;, Springer-Verlag (2005) ISBN 3540242171&amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
:&amp;lt;math&amp;gt;\frac{r d\theta}{B_\theta} = \frac{Rd\varphi}{B_\varphi}&amp;lt;/math&amp;gt;&lt;br /&gt;
&lt;br /&gt;
where &amp;lt;math&amp;gt;\phi&amp;lt;/math&amp;gt; and &#039;&#039;&amp;amp;theta;&#039;&#039; are the [[Toroidal coordinates|toroidal and poloidal angles]], respectively. &lt;br /&gt;
Thus &amp;lt;math&amp;gt;q = m/n = \left \langle d\varphi /d\theta \right \rangle &amp;lt;/math&amp;gt; can be approximated by&lt;br /&gt;
&lt;br /&gt;
:&amp;lt;math&amp;gt;q \simeq \frac{r B_\varphi}{R B_\theta}&amp;lt;/math&amp;gt;&lt;br /&gt;
&lt;br /&gt;
Where the poloidal magnetic field &amp;lt;math&amp;gt;{B_\theta}&amp;lt;/math&amp;gt; is mostly produced by a toroidal plasma current. The principal significance of the safety factor &#039;&#039;q&#039;&#039; is that if &amp;lt;math&amp;gt;q \leq 2&amp;lt;/math&amp;gt; at the last closed flux surface (the edge), the plasma is [[:Wikipedia:Magnetohydrodynamics|magnetohydrodynamically]] unstable.&amp;lt;ref&amp;gt;Wesson J 1997 Tokamaks 2nd edn (Oxford: Oxford University Press) p280 ISBN 0198509227&amp;lt;/ref&amp;gt;&lt;br /&gt;
&lt;br /&gt;
In [[Tokamak|tokamaks]] with a [[divertor]], &#039;&#039;q&#039;&#039; approaches infinity at the [[separatrix]], so it is more useful to consider &#039;&#039;q&#039;&#039; just inside the separatrix. It is customary to use &#039;&#039;q&#039;&#039; at the 95% flux surface (the flux surface that encloses 95% of the poloidal flux), &#039;&#039;q&amp;lt;sub&amp;gt;95&amp;lt;/sub&amp;gt;&#039;&#039;.&lt;br /&gt;
&lt;br /&gt;
== See also ==&lt;br /&gt;
&lt;br /&gt;
* [[Magnetic island]]&lt;br /&gt;
* [[Magnetic shear]]&lt;br /&gt;
&lt;br /&gt;
== References ==&lt;br /&gt;
&amp;lt;references /&amp;gt;&lt;/div&gt;</summary>
		<author><name>Odstrcilt</name></author>
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