Field-reversed configuration

Field-reversed configuration: a toroidal electric current is induced inside a cylindrical plasma, creating a poloidal magnetic field, reversed in respect to the direction of an externally applied magnetic field. The resultant high-beta axisymmetric compact toroid is self-confined.

A field-reversed configuration (FRC) is a device developed for magnetic confinement fusion research that confines a plasma on closed magnetic field lines without a central penetration.^[1]

History

The FRC was first observed in laboratories in the late 1950s during theta pinch experiments with a reversed background magnetic field.^[2] The first studies of the effect started at the United States Naval Research Laboratory (NRL) in the 1960s. Considerable data has been collected since then, with over 600 published papers.^[3] Almost all research was conducted during Project Sherwood at Los Alamos National Laboratory (LANL) from 1975 to 1990,^[4] and during 18 years at the Redmond Plasma Physics Laboratory of the University of Washington,^[5] with the large s experiment (LSX).^[6] More recently some research has been done at the Air Force Research Laboratory (AFRL),^[7] the Fusion Technology Institute (FTI) of the University of Wisconsin-Madison^[8] and the University of California, Irvine.^[9] Some private companies now theoretically and experimentally study FRCs in order to use this configuration in future fusion power plants they try to build, like General Fusion, Tri-Alpha Energy, Inc., and Helion Energy.^[10]

The FRC is also considered for deep space exploration, not only as a possible nuclear energy source, but as means of accelerating a propellant to very high levels of specific impulse (I_sp) for electrically powered spaceships and fusion rockets, with interest expressed by NASA^{[11][12][13][14][15][16]} and the media.^[17][18]

Operation

One approach to producing fusion power is to confine the plasma with magnetic fields. This is most effective if the field lines do not penetrate solid surfaces but close on themselves into circles or toroidal surfaces. The mainline confinement concepts of tokamak and stellarator do this in a toroidal chamber, which allows a great deal of control over the magnetic configuration, but requires a very complex construction. The field-reversed configuration offers an alternative in that the field lines are closed, providing good confinement, but the chamber is cylindrical, allowing simpler, easier construction and maintenance.^[19]

Field-reversed configurations and spheromaks are together known as compact toroids. Unlike the spheromak, where the strength of the toroidal magnetic field is similar to that of the poloidal field, the FRC has little to no toroidal field component and is confined solely by a poloidal field. The lack of a toroidal field means that the FRC has no magnetic helicity and that it has a high beta. The high beta makes the FRC attractive as a fusion reactor and uniquely suited to aneutronic fuels because of the low required magnetic field. Spheromaks have β ≈ 0.1 whereas a typical FRC has β ≈ 1.^[20][21]

Formation

In modern FRC experiments, the plasma current that reverses the magnetic field can be induced in a variety of ways.

When a field-reversed configuration is formed using the theta-pinch (or inductive electric field) method, a cylindrical coil first produces an axial magnetic field. Then the gas is pre-ionized, which "freezes in" the bias field from a magnetohydrodynamic standpoint, finally the axial field is reversed, hence "field-reversed configuration." At the ends, reconnection of the bias field and the main field occurs, producing closed field lines. The main field is raised further, compressing and heating the plasma and providing a vacuum field between the plasma and the wall.^[22]

Neutral beams are known to drive current in Tokamaks^[23] by directly injecting charged particles. FRCs can also be formed, sustained, and heated by application of neutral beams.^[21][24] In such experiments, as above, a cylindrical coil produces a uniform axial magnetic field and gas is introduced and ionized, creating a background plasma. Neutral particles are then injected into the plasma. They ionize and the heavier, positively-charged particles form a current ring which reverses the magnetic field.

Spheromaks are FRC-like configurations with finite toroidal magnetic field. FRCs have been formed through the merging of spheromaks of opposite and canceling toroidal field.^[25]

Rotating magnetic fields have also been used to drive current.^[26] In such experiments, as above, gas is ionized and an axial magnetic field is produced. A rotating magnetic field is produced by external magnetic coils perpendicular to the axis of the machine, and the direction of this field is rotated about the axis. When the rotation frequency is between the ion and electron gyro-frequencies, the electrons in the plasma co-rotate with the magnetic field (are "dragged"), producing current and reversing the magnetic field. More recently, so-called odd parity rotating magnetic fields^[27] have been used to preserve the closed topology of the FRC.

Plasma stability

Charged particles inside an FRC follow large betatron orbits (their average gyroradius is about half the size of the plasma) which are typical in accelerator physics rather than plasma physics. FRCs are very stable because the plasma is not dominated by usual small gyroradius particles like other thermodynamic equilibrium or nonthermal plasmas. Its behavior is not described by classical magnetohydrodynamics, hence no Alfvén waves and almost no MHD instabilities despite their theoretical prediction,^[28] and it avoids the typical "anomalous transport", i.e. all processes in which loss of particles or energy occurs.^[29][30][31]

As of 2000, several remaining instabilities are being studied:

• The tilt and shift modes. Those instabilities can be mitigated by either including a passive stabilizing conductor, or by forming very oblate plasmas (i.e. very elongated plasmas),^[32] or by creating a self-generated toroidal field.^[33] The tilt mode has also been stabilized in FRC experiments by increasing the ion gyroradii.^[34]
• The magnetorotational instability. This mode causes a rotating elliptical distortion of the plasma boundary, and can destroy the FRC when the distorted plasma comes in contact with the confinement chamber.^[35] Successful stabilization methods include the use of a quadrupole stabilizing field,^[36][37] and the effects of a rotating magnetic field (RMF).^[38][39]

Experiments

Selected field reverse experiments, pre-1988^[3]

Year	Device	Location	Device length	Device diameter	B-field	Fill pressure	Confinement	Studied
			Meter	Meter	Tesla	Pascal	Seconds
1959	-	NRL	0.10	0.06	10.00	13.33	2.E-06	Annihilation
1961	Scylla I	LASL	0.11	0.05	5.50	11.33	3.E-06	Annihilation
1962	Scylla III	LASL	0.19	0.08	12.50	11.33	4.E-06	Rotation
1962	Thetatron	Culham	0.21	0.05	8.60	13.33	3.E-06	Contraction
1962		Julich	0.10	0.04	6.00	30.66	1.E-06	Formation, tearing
1963		Culham	0.30	0.10	5.00	6.67	6.E-06	Contraction
1964	0-PII	Garching	0.30	0.05	5.30	13.33	1.E-06	Tearing, contraction
1965	Pharos	NRL	1.80	0.17	3.00	8.00	3.E-05	Confinement, rotation
1967	Centaur	Culham	0.50	0.19	2.10	2.67	2.E-05	Confinement, rotation
1967	Julietta	Julich	1.28	0.11	2.70	6.67	2.E-05	Tearing
1971	E-G	Garching	0.70	0.11	2.80	6.67	3.E-05	Tearing, rotation
1975	BN	Kurchatov	0.90	0.21	0.45	0.27 - 1.07	5.E-05	Formation
1979	TOR	Kurchatov	1.50	0.30	1.00	0.27 - 0.67	1.E-04	Formation
1979	FRX-A	LASL	1.00	0.25	0.60	0.53 - 0.93	3.E-05	Confinement
1981	FRX-B	LANL	1.00	0.25	1.30	1.20 - 6.53	6.E-05	Confinement
1982	STP-L	Nagoya	1.50	0.12	1.00	1.20	3.E-05	Rotation
1982	NUCTE	Nihon	2.00	0.16	1.00		6.E-05	Confinement, rotation
1982	PIACE	Osaka	1.00	0.15	1.40		6.E-05	Rotation
1983	FRX-C	LANL	2.00	0.50	0.80	0.67 - 2.67	3.E-04	Confinement
1984	TRX-1	MSNW	1.00	0.25	1.00	0.67 -2.00	2.E-04	Formation, confinement
1984	CTTX	Penn S U	0.50	0.12	0.40	13.33	4.E-05	Confinement
1985	HBQM	U Wash	3.00	0.22	0.50	0.53 - 0.93	3.E-05	Formation
1986	OCT	Osaka	0.60	0.22	1.00		1.E-04	Confinement
1986	TRX-2	STI	1.00	0.24	1.30	0.40 - 2.67	1.E-04	Formation, confinement
1987	CSS	U Wash	1.00	0.45	0.30	1.33 - 8.00	6.E-05	Slow formation
1988	FRXC/LSM	LANL	2.00	0.70	0.60	0.27 - 1.33	5.E-04	Formation, confinement
1990	LSX	STI/MSNW	5.00	0.90	0.80	0.27 - 0.67		Stability, confinement

Selected field reverse configurations, 1988 - 2011^[40]

Device	Institution	Device type	Electron density	Max ion or electron	FRC diameter	Length/diameter
			10E19 / Meter^3	Temperature [eV]	[Meter]
Spheromak-3	Tokyo University	Merging spheromak	5.0 – 10.0	20 – 100	0.40	1.0
Spheromak-4	Tokyo University	Merging spheromak		10 – 40	1.20 - 1.40	0.5 – 0.7
Compact Torus Exp-III	Nihon University	Theta-pinch	5.0 – 400.0	200 – 300	0.10 - 0.40	5.0 – 10.0
Field-Reversed Exp Liner	Los Alamos	Theta-pinch	1,500.0 – 2,500.0	200 – 700	0.03 - 0.05	7.0 – 10.0
FRC Injection Exp	Osaka University	Translation trapping	3.0 – 5.0	200 – 300	0.30 - 0.40	7.0 – 15.0
Swarthmore Spheromak Exp	Swarthmore	Merging spheromak	100	20 – 40	0.40	1.5
Magnetic Reconnection Exp	Princeton (PPPL)	Merging spheromak	5.0 – 20.0	30	1.00	0.3 – 0.7
Princeton Field Reverse Exp (PFRC)	Princeton (PPPL)	Rotating B-field	0.05 – 0.3	200 – 300	0.06
Translation Confinement Sustainment	University of Washington	Rotating B-field	0.1 – 2.5	25 – 50	0.70 - 0.74
Translation Confinement Sustainment-Upgrade	University of Washington	Rotating B-field	0.4 – 1.5	50 – 200	0.70 - 0.74	1.5 – 3.0
Plasma Liner Compression	MSNW	Translation trapping			0.20
Inductive Plasma Accelerator	MSNW	Merging collision	23.0 – 26.0	350	0.20
Inductive Plasma Accelerator-C	MSNW	Merging compression	300.0	1200 - 2000	0.2	10.0
Colorado FRC	University of Colorado	Merging spheromak
Irvine Field Reverse Configuration	UC Irvine	Coaxial source	150.0	10	0.60
C-2	Tri Alpha Energy, Inc.	Merging collision	5.0 – 10.0	200 – 500	0.60 - 0.80	3.0 – 5.0

See also

• List of plasma (physics) articles

External links

• Google techtalks: Nuclear Fusion: Clean Power for the Next Hundred Centuries
• University of Washington " FRC Introduction"

References

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