High energy plasma generator using radio frequency and neutral beam power

Abstract

An apparatus for generating high energy plasma employs a low energy neutral beam injected into a magnetically contained mirror plasma to generate plasma ions that are boosted to fusion levels by a coordinated radio frequency field.

Description

[0001] Cross-reference to related applications

[0002] This application claims the benefit of U.S. Patent Application 16 / 839,780, filed April 3, 2020, which is incorporated herein by reference. Background Technology

[0003] The present invention relates to apparatus for generating high-energy plasmas that can promote nuclear fusion, and particularly to systems using magnetic mirror confinement and neutral beam injection, as well as additional radio frequency power injection.

[0004] Using a magnetic mirror confinement system, high-temperature plasma can be confined away from its physical container, preventing damage to the container and potential plasma quenching. This confinement system provides an axial magnetic field extending between the two ends where the flux lines converge. Plasma ions moving within this axial magnetic field undergo helical motion along the flux lines at a local cyclotron frequency and are “reflected” by the axial component of the magnetic force acting on the helical ions. This reflected magnetic force, caused by the convergence of the flux lines and the accompanying increase in magnetic field strength, is in a direction away from the convergence. Furthermore, the reflected force is proportional to the particle kinetic energy component perpendicular to the magnetic field. A similar reflected force acts on plasma electrons.

[0005] Nuclear fusion can be facilitated in magnetic mirror confinement systems by generating plasmas with sufficiently high energy and density. One method to achieve this high energy / density state is to inject electrically neutral particles (a neutral beam) through a magnetically enclosed field into the plasma, where the neutral particles in the neutral beam are ionized, i.e., split into plasma ions and plasma electrons. The neutral beam has an initial energy higher than that required for fusion, so that even with the expected collisional losses of the plasma ions after introduction into the plasma, the resulting plasma ions can maintain fusion-suitable energy. The plasma density and energy are determined by the loss rate of fast ions injected through the neutral beam, which decreases as the beam energy increases; therefore, high-energy ions are better confined than low-energy ions.

[0006] From an energy perspective, generating a sufficient flux of high-energy particles with enough energy to sustain high fusion output in a magnetic mirror confinement system is difficult and expensive. Currently, this method does not appear to be suitable for generating net fusion energy. Summary of the Invention

[0007] This invention also injects a neutral beam into a magnetic mirror confinement, but unlike previous methods, it uses a low-energy neutral beam with energy far less than that required to directly produce significant fusion. Instead, after the neutral beam is ionized, the energy of the fast ions from these neutral beam sources is boosted within the magnetically contained volume using a radio frequency electric field. By controlling the injection angle and energy of the neutral beam, the difficulty of preferentially transferring radio frequency energy to fast neutral beam ions rather than hot ions is overcome, resulting in a well-defined "turning point" for the fast ions in the magnetically contained field. At the turning point, the radio frequency wave is tuned to a multiple of the cyclotron frequency (i.e., a harmonic), preferentially exciting these neutral beam-injected ions to a fusion level with only a small expected wave damping effect on hot ions.

[0008] Specifically, in one embodiment, the invention provides an apparatus for generating high-energy plasmas in a magnetic mirror containment field, the magnetic mirror containment field providing axially extending magnetic flux lines converging at opposite first and second ends of a containment volume that holds the plasma. A neutral beam generator guides a neutral beam of particles into the containment volume at a predetermined angle and energy range relative to the magnetic field, such that the particles dissociate into plasma ions within the containment volume at the same angle and have a well-defined inflection point. At the inflection point, fast ions possess purely vertical energy. A radio frequency generator can then be used to generate an electric field that accelerates the beam-sourced ions to sufficient energy for plasma ion fusion.

[0009] Therefore, at least one embodiment of the present invention is characterized by providing a system for increasing the energy of plasma ions after they are injected into an enclosing field, thereby greatly improving the efficiency of the neutral beam.

[0010] The frequency of the electric field can be functionally dependent on the cyclotron frequency of the plasma ions in the neutral beam within the magnetic mirror containment field at the inflection point.

[0011] Therefore, at least one embodiment of the present invention is characterized by preferentially depositing energy in plasma ions having a matching cyclotron frequency.

[0012] In one implementation, the frequency of the electric field can be a harmonic of the cyclotron frequency at the inflection point, and the frequency of the electric field is greater than the cyclotron frequency.

[0013] Therefore, at least one embodiment of the present invention is characterized by utilizing the preferential transfer of radio frequency electrical energy generated at higher cyclotron harmonics to resonant fast ions.

[0014] The energy of the neutral beam was set such that more than 50% of the neutral beam particles were converted into plasma ions.

[0015] Therefore, at least one embodiment of the present invention is characterized by allowing the use of a low-energy neutral beam, which is suitable for higher particle flux and thus enables the achievement of high plasma density.

[0016] Neutral beams can have energies of less than 50,000 electron volts.

[0017] Therefore, at least one embodiment of the present invention is characterized by allowing a trade-off between high flux rate and high energy in the design of the neutral beam generator, thereby improving the ion fuel supply rate.

[0018] Radio frequency generators can boost the energy of plasma ions from a neutral beam by more than two times.

[0019] Therefore, at least one embodiment of the present invention is characterized by providing a significant energy boost to plasma ions after injection.

[0020] The radio frequency generator may include an antenna positioned close to the reflection limit of the plasma ions and generating a rotating electric vector perpendicular to the axis of the magnetic mirror containment field.

[0021] Therefore, at least one embodiment of the present invention is characterized by an optimized antenna for energy deposition of plasma ions.

[0022] The angle of the neutral beam can be between 15° and 80° relative to the axis.

[0023] Therefore, at least one embodiment of the present invention is characterized by providing a good trade-off between the energy of the neutral beam and the inflection point that isolates the neutral beam from thermionic ions.

[0024] The device also includes a processing volume that at least partially surrounds the containing volume to receive high-energy neutrons passing through the containing volume, and the processing volume contains elements for transmutation into different elements.

[0025] Therefore, at least one embodiment of the present invention is characterized by providing a system for treating materials with neutrons, for example, to manufacture radiopharmaceuticals or to regenerate spent nuclear fuel.

[0026] The neutral beam can be selected from the group consisting of deuterium and tritium, and in some embodiments, the system can use deuterium only for the neutral beam and the gas in the containment volume.

[0027] Therefore, at least one embodiment of the present invention is characterized by providing a system that can work with well-known neutral beam materials and, in some cases, can avoid the use of tritium and instead use deuterium.

[0028] In one embodiment, the present invention can be used to manufacture a fusion device having a reaction volume that holds fusionable material within a first axially extending magnetic containment field. In this embodiment, a first plasma plug and a second plasma plug may be located on opposite sides of the reaction volume along an axis, each plasma plug being a device for generating high-energy plasma as described above, wherein plasma ions escaping from the first and second plasma plugs generate a fusion reaction within the reaction volume.

[0029] Therefore, at least one embodiment of the present invention is characterized by providing an improved design for fusion devices used to provide transmutation or power generation.

[0030] These specific objectives and advantages may apply only to some embodiments falling under the claims, and therefore do not limit the scope of the invention. Attached Figure Description

[0031] Figure 1 This is a perspective cross-sectional view of a first embodiment of the present invention, which provides a magnetic mirror containing field, a neutral beam generator for guiding a beam into the containing volume, and a radio frequency generator for generating an electric field acting on plasma ions from the neutral beam generator.

[0032] Figure 2 yes Figure 1 A side-view frontal view of the flux lines of the containment volume, aligned with end views of these flux lines; both views show the trajectories of plasma ions at different energies and graphs relating cyclotron frequency, residence time, and electric field strength to axial distance; and

[0033] Figure 3 This is a simplified front cross-section of the fusion device, which employs... Figure 1 The magnetic mirror containment field acts as a plug to prevent high-energy plasma ions from escaping from the central solenoid magnetic field unit. Detailed Implementation

[0034] Now refer to Figure 1 The high-energy plasma system 10 can provide a pressure vessel 12, for example, in the form of a sealed cylindrical shell made of stainless steel or the like, which extends along axis 14 to receive a reaction gas, such as deuterium or tritium, from a pressure vessel or the like (not shown) through a valve inlet assembly 13.

[0035] The first electromagnetic coil 16a and the second electromagnetic coil 16 may be positioned within the pressure vessel 12 near opposite ends of the pressure vessel 12 to define an enclosing volume 17 with a magnetic enclosing field 15 between the first electromagnetic coil 16a and the second electromagnetic coil 16. The electromagnetic coils 16 are oriented and separated to form Helmholtz pairs aligned along axis 14 for establishing an axial BO field between the electromagnetic coils 16. In one embodiment, the electromagnetic coil 16 may be a flat coil provided to be helical about axis 14, and the electromagnetic coil 16 is powered by an externally controllable DC power supply 18 of a type known in the art.

[0036] Positioned between, but close to, one of the electromagnetic coils 16b is a radio frequency antenna 19 (shown in simplified form), which, for example, provides a circularly polarized radio field extending along axis 14 when driven by radio frequency generator 20. As understood in the art, the polarized radio field provides an electric vector 21 perpendicular to axis 14 and rotating about axis 14. Further discussion of loop antennas suitable for this purpose can be found in THStix's "Fast Wave Heating of a Two-Component Plasma" in Nuclear Fusion 15, 737 (1975) and RWHarvey, MGMcCoy, GDKerbel, and SCChiu's "ICRF Fusion Reactivity Enhancements in Tokamaks" in Nuclear Fusion 26, 43 (1986) (Nuclear Fusion 26, 43) (The above references are incorporated herein by reference.

[0037] A processing volume 22, for example in the form of a concentric outer cylindrical can, may be positioned radially outside the pressure vessel 12. This processing volume 22 may be filled with, for example, materials for the passage of high-energy neutrons, such as medical isotopes. 99 Mo(molybdenum 99), 131 I(iodine 131), 133 Xe (xenon 133) and 177 The aqueous material transmuted from the precursor of Lu (lutetium-177), or the processing volume 22 can support the support for the spent nuclear fuel rods that are regenerated by transmutation with high-energy neutrons.

[0038] Neutral beam generator 26 is positioned to inject a beam 28 of neutral particles 29 (i.e., non-ionized particles with a net charge of zero) into containment volume 17 at an angle θ. The angle θ is defined as the acute angle between the angle of beam 28 and axis 14. For example, the neutral particles 29 are atoms of deuterium or tritium introduced through gas line 24 and ionized by a localized plasma (not shown). As is generally understood in the art, these ions are accelerated in accelerator chamber 27 having a continuous set of charged plates. The ions then pass through neutralization gas unit 31 to generate neutral particles 29 through a charge exchange process that produces the beam 28.

[0039] Still referencing Figure 2 The magnetic flux lines 30 generated by coil 16 will produce a "bottle" shape that expands radially from axis 14 at the midpoint between coils 16 and contracts radially at the location of coil 16. As is generally understood in the art, this configuration produces a mirror-enclosed volume in which randomly distributed "hot" plasma ions 32 with sufficient inclination spiral around flux lines 30 between regions defined by inflection point 34.

[0040] As understood in the art, these thermal plasma ions can be established in a variety of ways, for example by using a radio frequency antenna 19 (albeit with lower efficiency) or by using a separate heating system that generates electron cyclotron resonance heating.

[0041] At the inflection point 34, the thermal plasma ions 32 reverse direction, caused by the increase in the axial component of the magnetic Lorentz force resulting from the convergence of flux lines 30. The frequency 35 of the spiral around flux lines 30 is called the "cyclotron frequency," and this frequency 35 is a function of the strength of the magnetic field 37 along axis 14, and for this reason, the cyclotron frequency 35 generally increases toward the electromagnetic coil 16. For ions of equal mass and charge, the cyclotron frequency will nominally be the same at a given position along axis 14, regardless of the ion's velocity or energy; however, ions 32 of equal mass with different inflection angles will generally have different inflection points 34.

[0042] The velocities and therefore energies of the neutral particles 29 in the neutral beam 28, as well as the tilt angle θ of the neutral beam 28, are set such that most, for example, greater than 50%, of the particles in the neutral beam 28 will be ionized into plasma ions 36 within the containing volume 17 before leaving the containing field. These plasma ions 36, now carrying a charge and at the same tilt angle, are captured by the magnetic flux lines 30 to increase the plasma density.

[0043] To facilitate this trapping of most of the neutral particles 29 in the neutral beam 28, the energy of the neutral beam 28 is limited to provide sufficient flight time for the neutral particles 29 to be ionized. Typically, the desired energy of the neutral beam 28 for ionization will be much lower than the kinetic energy required for substantial fusion, and is typically less than 100,000 electron volts or preferably less than 50,000 electron volts, and more typically on the order of approximately 15 to 25 keV. This contrasts with prior art methods, which require energies of the neutral particles 29 exceeding those required to promote fusion between plasma ions 36, and typically exceeding one million electron volts for DD fusion. By limiting the energy of the neutral beam 28, a trade-off can be achieved in the shared neutral beam generator 26 to produce a higher flux density of neutral particles 29, thereby also increasing the plasma density.

[0044] Still refer to Figure 1 and Figure 2 The tilt angle θ of the neutral beam 28 is selected such that the resulting plasma ions 36 provide a predetermined inflection point 34' along the axis 14, and thus a corresponding predetermined cyclotron frequency 35 of the plasma ions 36 is provided at the inflection point 34'. This cyclotron frequency is used to set the frequency of the radio frequency generator 20, as will be discussed below.

[0045] In addition, antenna 19 is positioned near a turning point 34' to provide maximum field strength in that region.

[0046] Finally, within the energy level provided by the neutral beam 28 for the desired capture of the neutral particles 29 within the containment volume 17, the energy of the neutral beam 28 is set as high as possible, such that the orbital radius of the plasma ions 36 generated by the neutral beam 28 (rotational orbit 52) ​​is higher than the average distribution of the "thermal ions" 32, which are ions not directly obtained by the neutral beam 28.

[0047] Although the inventors do not wish to be bound by a particular theory, the above-mentioned: (a) setting the cyclotron frequency of the radio frequency generator 20 at the inflection point 34' to a harmonic of the cyclotron frequency of the plasma ions 36, (b) boosting the energy of the plasma ions 36 to a value higher than the average distribution value of the thermal plasma ions 32, and (c) maximizing the electric field strength at the inflection point 34', all work together to allow the radio frequency generator 20 to preferentially boost the energy of the plasma ions 36 from the neutral beam 28 without being affected by the damping of the thermal plasma ions 32.

[0048] In this respect, the setup of the radio frequency generator 20 (according to (a)) provides preferential coupling with plasma ions 36 having a matched (e.g., harmonic-dependent) cyclotron frequency 35, compared to thermal plasma ions 32 with a range of different Doppler shift cyclotron frequencies and inefficient coupling. This coupling can be coupled with the Bessel function B. n-1 (k ⊥ *v ⊥ / ω ci Proportional, in this function:

[0049] n is the resonant cyclotron harmonic number of the injected wave.

[0050] k ⊥ It is the vertical wavenumber, and

[0051] ω ci It is the cyclotron frequency of the resonant ion.

[0052] k ⊥ / ω ci The amount may be ~v A That is, the Alfvén velocity of the ions (see TH Stix in Nuclear Fusion 15, 737 (1975) on “Fast Wave Heating of a Two-Component Plasma”). This takes into account the Bessel function for v. ⊥ The coupling is dependent on the vertical velocity of the ions, and the coupling can be tuned to preferentially dampen the hot tail ions from the neutral beam and those hot tail ions that diffuse to higher energies via the radio frequency wave.

[0053] Furthermore, by setting the frequency of the radio frequency generator 20 according to the cyclotron frequency 35 at the turning point 34', the effect of the electric field from the radio frequency generator 20 on the plasma ions 36 is increased due to the extended residence time 50 of the plasma ions 36 at the turning point 34' during their minimum axial velocity. For example, this is in contrast to the thermal plasma ions 32, which move rapidly through this region to another turning point 34 or do not reach as far as the turning point 34'.

[0054] As described above, by increasing the energy of plasma ions 36 to a value higher than that of thermal plasma ions 32 (according to (b)), and by setting the RF generator 20 to an RF frequency that is a higher harmonic of the cyclotron frequency 35 of the plasma ions 36, the higher-energy plasma ions 36 with a larger radius cyclotron orbit 52 preferentially absorb power compared to the thermal plasma ions 32 with a smaller cyclotron orbit 52. In some embodiments, the RF frequency may be set to a range of 20 MHz to 100 MHz and / or a harmonic n greater than n=2 and preferably n=4.

[0055] Typically, as the number of Bessel functions associated with those harmonics increases, higher harmonics enhance the relationship between energy absorption and the gyroscopic orbit 52. Specifically, energy absorption will be related to J n-1 (k ⊥ ρ) is proportional, where: J n-1 ρ is the Bessel coefficient for a given harmonic n; ρ is the radius of the orbit 52 of the particle around the magnetic flux line 30, which is based on It increases with increasing energy; and k ⊥ It is the wavenumber of plasma ions 36, which is the polarization performance of the wave in the plasma and the antenna 19 that emits the wave.

[0056] It will be understood that this efficient preferential absorption of energy by plasma ions 36 will be self-reinforced as energy is absorbed and the rotational orbit of plasma ions 36 is increased.

[0057] Finally, by placing the highest field strength of antenna 19 near the inflection point 34', plasma ions 36 are preferentially affected.

[0058] Typically, the magnetic containment field 15 will tend to lose some plasma ions 32 with low tilt angles through its ends. These particles are referred to as being in the "loss cone". By increasing the number of plasma ions 36 with known tilt angles θ outside the loss cone, an increased plasma density can be obtained.

[0059] Although the desired setting of the cyclotron frequency of the plasma ions 36 near the inflection point 34', and therefore the frequency of the RF generator 20, is primarily a function of the vacuum magnetic field strength 37, the vacuum magnetic field strength 37 will change slightly as a function of increasing plasma density / pressure. Accordingly, the invention contemplates that either or both of the DC power supply 18 or the RF generator 20 can be adjusted during operation to maintain the aforementioned relationship that promotes energy transfer to the plasma ions 36. In particular, such adjustment can be performed via closed-loop feedback control using a sensor 56 that detects plasma pressure, for example using a diamagnetic ring that measures the weakening of the magnetic field due to increased plasma pressure, to ensure that the excitation frequency of the RF generator 20 matches the actual and dynamic cyclotron frequency 35 at the inflection point 34'. To some extent, the cyclotron frequency is determined by the total field (the vacuum field from the coil plus the plasma diamagnetic); the invention also contemplates that it may not be necessary to change the frequency, but the location of the inflection point will be moved closer to the electromagnetic mirror coil.

[0060] Now refer to Figure 3 The benefits of this invention in providing high plasma density make it suitable as part of a system in which two high-energy plasma systems 10 can be used as “plugs” to capture high-energy plasma ions in a large neutron generator 60 for transmutation (as described above) or fusion power generation purposes. For example, such a design can use tandem mirror schemes as described by G. Dimov, V. Zakaidakov and M. Kishinevski in Fiz. Plazmy 2 597 (1976) (Fiz. Plazmy Vol. 2, p. 597 (1976)), Sov. J. Plasma, Phys 2, 326 (1976) (Sov. J. Plasma Phys Vol. 2, p. 326 (1976)), and TK Fowler and BG Logan in Comments on Plasma Physics and Controlled Fusion 2, 167 (1977) (Comments on Plasma Physics and Controlled Fusion, Vol. 2, p. 167 (1977)), and the aforementioned literature is incorporated herein by reference.

[0061] More specifically, in this tandem mirror neutron generator 60, a first high-energy plasma system 10a and a second high-energy plasma system 10b are positioned opposite each other along axis 14 on either side of the generator volume 62. Typically, the high-energy plasma system 10 will have an axial length of approximately 2 meters, while the generator volume 62 will be much larger, for example, approximately 50 meters or more.

[0062] The electromagnetic coils 16 in both high-energy plasma systems 10a and 10b can be axially aligned to provide the same polarization direction of the magnetic field along a common axis 14. Therefore, the flux line 30 of the first high-energy plasma system 10a can continue through volume 62 to the second high-energy plasma system 10b. Within volume 62, the flux line 30 is focused by a solenoid coil 66 extending axially around axis 14 of volume 62.

[0063] For this purpose, the electromagnetic coil 16 may be a superconducting magnet, for example, according to “Smaller and sooner: Exploiting high magnetic fields from new superconductors for a more attractive fusion energy development path” in the Journal of Fusion Energy, 35, 41 (2016), which is also incorporated herein by reference.

[0064] A subset of thermal plasma ions 32, with a uniformly distributed tilt angle and having been boosted to higher energies through kinetic transfer from plasma ions 36, can escape from the high-energy plasma system 10 into a volume 62 containing a reactive gas, such as deuterium or tritium, to facilitate fusion and the emission of neutrons 64 from the volume 62. The high pressure of the high-energy plasma system 10 prevents the escape of high-energy plasma ions from the volume 62 to maintain a high density for significant fusion.

[0065] Volume 62 may be surrounded by containing volume 22, which may include heat exchanger fluid 68, for example, working fluid 70 for receiving, through one or more heat exchangers, such as for use in thermodynamic engines like turbines to generate electricity. Alternatively, containing volume 22 may be used for transmutation of materials to produce medical isotopes or to regenerate spent nuclear fuel, as discussed above.

[0066] This application incorporates the disclosures of U.S. Patent Application 2019 / 0326029 entitled "Apparatus and Method for Generating Medical Isotopes" and U.S. Patent Application 2013 / 0142296 entitled "Apparatus and Method for Generating Medical Isotopes," which describe additional techniques for managing isotope transmutation, including the use of a neutron multiplier generator and other construction details and mechanisms for generating the aforementioned neutral beams.

[0067] Certain terms used herein are for illustrative purposes only and are therefore not intended to be limiting. For example, terms such as “upper,” “lower,” “above,” and “below” refer to orientations in the accompanying drawings. Terms such as “front,” “rear,” “rear,” “bottom,” and “side” describe the orientation of parts of a component within a consistent but arbitrary frame of reference, which becomes clear by referring to the text describing the component in question and the associated drawings. Such terms may include words specifically mentioned above, their derivatives, and words with similar meanings. Similarly, the terms “first,” “second,” and other such numerical terms relating to structures do not imply order or sequence unless the context clearly indicates otherwise.

[0068] When describing elements or features of this disclosure and exemplary embodiments, the articles “a,” “an,” “the,” and “described” are intended to indicate the presence of one or more such elements or features. The terms “comprising,” “including,” and “having” are intended to be inclusive and mean that additional elements or features may be present in addition to those specifically stated. It should also be understood that the method steps, processes, and operations described herein are not to be construed as requiring them to be performed in the specific order discussed or illustrated, unless explicitly identified as such. It should also be understood that additional or alternative steps may be employed.

[0069] It is specifically intended that the invention is not limited to the embodiments and illustrations contained herein, and that the claims be understood to include modifications of these embodiments, including portions of embodiments within the scope of the appended claims and combinations of elements of different embodiments. The entire contents of all publications, including patent and non-patent publications, described herein are incorporated herein by reference.

Claims

1. An apparatus for generating high-energy plasma, comprising: A magnetic mirror containment field that provides axially extending magnetic flux lines that converge at opposite first and second ends that maintain the containment volume of the plasma. A neutral beam generator guides a neutral beam of particles at a predetermined angle and energy into the containing volume, causing the particles to dissociate into plasma ions within the containing volume, wherein the energy of the neutral beam of the particles is less than the energy required for plasma ion fusion. as well as A radio frequency generator that generates an electric field that accelerates the plasma ions to sufficient energy for plasma ion fusion, wherein the frequency of the electric field is functionally dependent on the cyclotron frequency of the plasma ions in the neutral beam within the magnetic mirror containment field at the inflection point.

2. The device according to claim 1, wherein, The frequency is a harmonic of the cyclotron frequency, and the frequency is greater than the cyclotron frequency.

3. The device according to claim 1, wherein, The energy of the neutral beam is set such that more than 50% of the neutral beam particles are converted into plasma ions.

4. The device according to claim 1, wherein, The neutral beam has an energy of less than 50,000 electron volts.

5. The device according to claim 1, wherein, The radio frequency generator increases the energy of the plasma ions from the neutral beam by more than two times.

6. The device according to claim 1, wherein, The radio frequency generator includes an antenna positioned close to the reflection limit of the plasma ions and generating a rotating electric vector perpendicular to the axis of the magnetic mirror containment field.

7. The device according to claim 6, wherein, The tilt angle relative to the axis is between 30° and 60°.

8. The apparatus of claim 1, further comprising a processing volume that at least partially surrounds the containing volume to receive high-energy neutrons passing through the containing volume, and the processing volume containing elements for transmutation into different elements.

9. The device according to claim 8, wherein, The element used for transmutation is selected from the precursor. 99 Mo、 131 I, 133 Xe and 177 Lu is a precursor to medical radioisotopes.

10. The device according to claim 8, wherein, The element used for transmutation is depleted nuclear fuel.

11. The device according to claim 1, wherein, The neutral beam is selected from the group consisting of deuterium and tritium.

12. The device according to claim 1, wherein, The neutral bundle is deuterium.

13. The device according to claim 1, wherein, The device includes a pair of magnetic coils that generate the magnetic mirror containment field, wherein the radio frequency generator provides an antenna between the magnetic coils, and wherein the containment volume is contained within an airtight chamber.

14. A fusion device, comprising: A reaction volume that holds the fusion material within a first axially extending magnetic containment field; A first plasma plug and a second plasma plug, the first plasma plug and the second plasma plug being located on opposite sides of the reaction volume along an axis; each plasma plug comprising: (a) A magnetic mirror containment field that provides axially extending magnetic flux lines that converge at opposite first and second ends that maintain the containment volume of the plasma. (b) A neutral beam generator that guides a neutral beam of particles at a predetermined angle and energy into the containing volume, such that the particles dissociate into plasma ions within the containing volume; and (c) A radio frequency generator that generates an electric field that accelerates the plasma ions to an energy higher than that of the particles entering the containment volume, wherein the frequency of the electric field is functionally dependent on the cyclotron frequency of the plasma ions of the neutral beam in the magnetic mirror containment field at the inflection point. Thus, the plasma ions escaping from the first and second plasma plugs generate a fusion reaction in the reaction volume.

15. The fusion device according to claim 14, wherein, The pressure of plasma ions in the first plasma plug and the second plasma plug is greater than the pressure of plasma ions in the reaction volume.

16. The fusion device of claim 15 further includes a generator that receives neutrons from the reaction volume to generate electrical energy.

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