METHOD AND APPARATUS FOR CONTROLLING CHARGED PARTICLES

Abstract: The charged particles comprise electrons and positive ions. A magnetic field having only point cusps is used to confine injected electrons and so to generate a negative potential well (600). Positive ions injected into the negative potential well are trapped therein. The preferred means for generating the magnetic field is current-carrying elements (800) arranged at positions corresponding to the edges of any of several truncated regular polyhedrons.

Description: METHOD AND APPARATUS FOR CONTROLLING CHARGED PARTICLES BACKGROUND OF THE INVENTION This invention pertains to a method and apparatus for controlling charged particles, and more particularly to a method and apparatus for confining ionized gases or plasmas . Confinement of dense ionized gases is a necessary step in several processes which are currently the object of intense research. These processes include nuclear fusion. Research on the confinement and heating of ionized gases and of their electron and ionic charged particle gaseous components has concentrated principally on the methods of inertial confinement and magnetic confinement. An example of non- magnetic and non-electric inertial con¬ finement is the so-called "laser-fusion" process in which large pressures are to be induced over the surface of small spheres of material which it is desired to heat and confine by the vaporization and "blowoff" of surface material by laser light energy heating thereof. Such high pressures cause the compression and resulting compressional heating of the material within the small spheres. The principal difficulty of achieving useful fusion-reaction-producing con¬ ditions by such hydrodynamic-inertial confinement means is that of the lack of stability of compression, to the very high densities required, of small amounts of material in spherical or other con¬ vergent geometries. In such inertial-compression schemes it is necessary to create the forces and drive the compression sufficiently rapidly that radiation and electron conduction energy loss processes from the compressing plasma/ material do not radiate and/ or carry away the material internal energy before the desired particle energy (i.e. , temperature) has been achieved.. Typically, time scales of fractions of microseconds are required for such systems. Attainable compression temperatures are limited by deviations from perfect symmetry of compression which lead to non- spherical compressed geometries, mixing of material, and other effects. Because of these requirements and physical difficulties such inertial- mechanical means for confining and heating plasma material have been shown to require large power input to the devices and machinery used for studies of such processes. This approach is of little interest in connection with and has no fundamental relevance to the present invention, and will not be further considered. In magnetic confinement methods, strong magnetic fields are used in various geometries in attempts to confine or hold plasmas in well-defined spatial regions for periods of time long enough to allow their heating to desired levels of plasma ion particle energy or temperature. An example of a device which employs a magnetic con¬ finement method is the tokamak. The tokamak has a toroidal magnetic confinement geometry in which plasma ions and electrons are to be held within a toroidal volume by the magnetic field lines which circle through that volume. Another example of such a device is a mirror machine. A mirror machine uses a "mirror" geometry in which opposing (facing) magnet coils act to provide a high-field surface around a central volume at lower field strength. Use of similarly-directed currents in such end coils causes "end-plugging" of a solenoidal field con¬ figuration, while oppositely-directed currents give rise to a bi-conic mirror geometry around a region in which the central magnetic field strength can drop to zero. This latter arrangement is described in more detail below. Charged particles (e.g. , plasma ions and/ or electrons) gyrate around (normal to) the magnetic field lines in all such systems, in orbits whose gyro radii are set by their individual par¬ ticle charge, mass, and energy of motion transverse to the magnetic fields. As just mentioned, one of the magnetic field geometries which have been studied for plasma confinement is the simple bi- conic mirror cusp geometry. Such a system is depicted in Figs. 1A-1C. In this system two opposing coils 100 and 110 carrying oppositely-directed currents face ("mirror") each other and produce a bipolar and equatorial field "cusp" geometry. The advantage of this system is that it is (i.e. , has been shown to be) inherently stable to macroscopic "collective" losses of plasma across the field. This is in contrast to the toroidal tokamak and to the solenoidal mirror geometries which are not inherently stable to such losses. Losses in the bi-conic mirror system are principally out through the polar end cusps one of which is labelled 130, and the belt or equatorial "ring" cusp 135 of the magnetic field geometry. Particles 140 making up plasma 120 approach point cusp 130 from a range of. angles. Most are deflected due to their having a nonaxial velocity component. Some particles, however, approach the cusp along paths which permits them to escape out through the cusp. The total loss rate through these cusp regions is determined by the "loss cone angle" and by the solid angle (in velocity space) subtended by the leakage cusp system. The loss cone angle is set by the field strength in the current-carrying coils which make the field, and the solid angle is simply the result of the geometry chosen. In the bi-conic mirror system the losses are predominantly through the equatorial cusp 135 because of its great extent entirely surrounding the plasma region. In experimental and theoretical work aimed at using such "mirror" field systems to confine plasmas, a remedy for this defect was attempted by twisting half the field through 90° (so-called "baseball" geometry) , so that the cusp leakage ring is split into orthogonal half-hemispheres. This has the effect of removing equatorial plane coherence for particles able to scatter out through the equatorial field ring loss angle. However, this twisting of the field half-space does not change the basic topology of the bi-conic system and, although still macroscopically stable, the plasma will continue to be lost predominantly through the (now-bifurcated) equatorial ring cusp in the confining field. Studies have also been made of the solenoidal mirror geometry, in which end point cusps act as "reflectors" of particles at the ends of the quasi-solenoidal field system. As previously noted, however, the solenoidal field region itself and its connection regions to the end cusps are inherently macro-unstable with respect to plasma/field interchange displacements. Thus, while the ring cusp losses of the bi-conic cusp; mirror geometry have been removed, they have been replaced by new losses due to instability of the basic central field configuration. In experimental and theoretical work on such systems a partial remedy for this defect was obtained by adding current-carrying conductors between the mirror coils, parallel to the coil system axis. These parallel conductors (sometimes called "Ioffe bars" , after their Soviet inventor) provide fields which yield longi¬ tudinal surface cusp geometries which are inherently stable, but which embody particle losses through the longitudinal line cusps thus formed between conductors. In addition, locally unstable regions still exist between the central longitudinal fields and the end mirror point cusps, which lead to enhanced losses. The virtue of the simple bi-conic mirror cusp field system is that it is inherently macroscopically stable and is thus subject only to microscopic plasma loss phenomena (e.g. , coUisional guiding center transport) . Its defect is the very large conical sector equatorial ring cusp loss region. Polar end point cusp losses can be made small in most systems of interest by use of large mirror field ratios (particle velocity-space loss cone angle is given by sin 2 Θ = EBo/Bm] , where Bo is field strength at plasma center and Bm is field strength on the mirror cusp axis) . In addition, the point cusps can be used easily for injection of plasma ions and/or electrons into the central region of such a magnetic confinement geometry. A mirror system which contained only point cusps would provide an ideal stable field/ confinement geometry. Some efforts have been expended investigating other geometries for magnetic plasma confinement. One such effort is that of R. Keller and I .R. Jones, "Confinement d' un Plasma par un Systeme Polyedrique a' Courant Alternatif " , Z . Naturforschg. Vol. 21 n, pp. 1085-1089 (1966) . Octahedral and truncated cube systems were explored. These are labeled 200 and 230 in Fig. 2. Keller and Jones noted that the octahedron has two symmetry axes A and B. The truncated cube system, on the other hand, has three axes of symmetry C , D, and E . KeUer and Jones experimentaUy explored neutral plasma heating and confinement by driving alternate interlaced co sets at a (high) frequency of 4.7 MHz. It should be noted that the two interlaced fields used in this work were of oppo¬ site type, one being solenoidal and the other opposing bi-conical; thus alternation between field sets/states caused an inversion of field direction with each half cycle. It is not clear that alternation bet¬ ween such states is most effective for plasma confinement or heating. However, losses are greatly reduced from those of a con¬ ventional bi-conic equatorial ring cusp system of comparable size. Stable confinement was obtained at the experimental conditions, with modest heating observed, and the presence of a "spherical wave" was noted in the plasma. Another extreme of magnetic confinement geometry is disclosed in U .S . Patent No. 4, 233, 537 to Limpaecher. Therein it is proposed to confine neutral plasmas within a cylindricaUy sym- metric volume whose surface contains an array of 1250 alternating magnetic poles, with axial electron injection to establish a negative plasma potential. In this system , plasma is to be confined by the surface magnetic multipole fields and constrained by the cylindrical interior negative electric potential field. In all of the arrangements considered there were always macroscopically unstable regions somewhere on the surface (e.g. , at the end regions of the cylindrical volume) , and the electrostatic field was never suggested as the primary or sole confinement field for plasma ions. In both magnetic and inertial-confinement approaches the plasma heating is made to occur by statistically random coUisional processes, either while under growing compression conditions or (with externaUy-driven energetic particles) while "trapped" for a sufficient length of time in a "confining" magnetic field geometry. It would appear to be desirable, however, to provide a more direct and non- statistical non-random process for energy addition to gain energy directly by "falling" through the ' negative electric potential which provides their confinement. In the tokamak (and all other magnetic confinement systems) configuration, charged particles are lost from the system (to its walls) by transport of plasma ions and electrons across the magnetic fields by microscopic inter-particle collisions (which abruptly shift the particle gyration radius "guiding center") , and by other processes in which plasma particles, ions, and electrons act coUectively to yield macroscopic transport losses of "groups" of par- tides across the supposed "confining" magnetic fields. Microscopic inter-particle collisions are both inevitable and necessary in plasmas in which it is desired to achieve inter-particle nuclear reactions. Thus in a plasma confinement system of interest for the attainment of nuclear fusion reactions, it is inherently necessary that plasma particles be lost from the field geometry by coUisional "jumping" of the gyro centers (above) . Without collisions there can be no fusion (or other nuclear) reactions; thus the attainment of conditions for fusion reactions ensures that the magne¬ tic field can not confine the plasma, but can only constrain its (inherent) loss rate. In short, magnetic fields can confine (without losses) only plasmas and charged particle systems in which no collisions occur between particles. Since collisions wiU occur if two or more par¬ tides are in a given magnetic field system , it is evident that magne- tic fields can not completely confine plasmas at densities of utility for nuclear fusion (or other nuclear) reaction production; they can only inhibit their unavoidable loss rate. In such systems the partide losses therefrom constitute an energy loss which must be made up by continuous injection of power to the system, in order to keep it operating at the desired conditions of plasma density and/or tern- perature. Research work to date in nudear fusion has shown that considerable losses are inherent in the use of magnetic fidds for plasma confinement. In general it has been found that conceptual magnetic con- finement systems for the production of useful fusion power generation must be very large when based on low-power-consumption magnet coils of super-conducting material. Alternatively it has been found that small tokamak systems with small power input to the plasma region can be based on magnet coils of normal-conducting materals but will require very large power input to drive these coils. Thus, aU conventional magnetic . approaches to the genera¬ tion of fusion power are practicaUy unable to take advantage of the natural large energy gain (G = ratio of energy output to energy input per fusion reaction) inherent in the fusion process. This "natural" gain can be as large as G = 2000 for the fusion of deuterium (D or H2) and tritium (T or H3) , the two heavy isotopes of hydrogen (p or Hx) . Furthermore, a magnetic fidd can not produce a force on a charged partide unless that partide is in motion. If it is at rest with respect to the system - and therefore not attempting to leave the system - it will not fed any force in a magnetic system. It wiU experience a force in such a system only if it is trying to escape from (or otherwise moving in) the system. When moving, the force exerted on such a charged partide by a magnetic field is not oppositely directed to its direction of motion, it is at right angles to its direction of motion. The magnetic force on such a moving partide is thus not a "restoring" force, it is a "deflecting" force. Because of this the field is rdatively ineffective in holding neutral plasmas of equal numbers of charged parti des together, as in tokamaks or mirror field geometries used in fusion research. This results in large power requirements for the machinery needed/ used for confinement and plasma heating in such devices constructed according to these concepts, and the energy gain (G ) potentiaUy achievable is found to be limited by practical engineering con- siderations to the order of G __i 2 to 6. Electrostatic systems have also been explored for the con¬ finement of plasmas. The simplest such system is that with a spherical geometry, in which a negative potential is maintained at the center of a spherical sheU by an electrode (cathode) mounted at the center. Positive ions introduced into such a geometry wiU be forced ' toward (and wiU "fall" to) the center until their mutual Coulombic repulsive forces exactly balance the inward-directed forces on them by the appUed radial fields. In this "faU" the ions wiU acquire partide energies equal to the electric fidd potential drop. In - principle-, such systems offer very effident means of reaching partide energies of interest for fusion reactions (effidency of energy addition and thus of partide "heating" by this means is nearly 100%, which enables the achievement of very high gain G values). Unfortunately the ion densities which can be achieved by this means, within the limits of externaUy-supplied dectric fidds which are practically attainable, are too small to be of interest for fusion plasma reaction production at a useful level. The absolute density of ions can be increased by the addi¬ tion of dectrons to such a system, to yidd a (net) neutral plasma whose ion and electron densities are grossly equal. However, it can be shown (Earnshaw' s theorem) that a (neutral) plasma can not be confined by an electrostatic field of this type. This is because the plasma ions and dectrons wUl be subject to oppositely-directed for¬ ces in the static field and wiU separate, thus producing a local fidd gradient (due to their charge separation) which exactly cancels the applied field. In this condition the plasma can move across the fidd as fast as electrons are lost from its outer boundary. The speed of motion of electrons escaping from such a system is limited to that of ion motion, as the two oppositely-charged partides are tied together by their dielectric fidd. In a system with a static centraUy-negative spherical electric fidd configuration, as described above, there is no force field to inhibit electron loss from the outer boundary or periphery of such a neutral plasma. Previous workers have recognized the value of dectrostatic forces for plasma/ ion confinement. The earliest work was reported by William C. Elmore, James L . Tuck, and Kenneth M . Watson, "On the Inertial-Electrostatic Confinement of a Plasma" , Phys. Fluids, Vol. 2, No. 3, pp. 239-246 (May-June 1959) . Elmore et al proposed to overcome the difficulty of the Earnshaw' s theorem limit (mentioned above) through the generation of the desired spherical radial field by the injection of energetic dectrons in a radiaUy-inward direction. This is depicted in Fig. 3. In this pioneering work electrons were to be emitted from the inner surface of a spherical sheU 300 through a (screen) grid 310 at high positive potential (100 kev) . Electrons so injected would pass through the grid and converge radiaUy to a central region 330 where their electrostatic potential at the sphere center was equal to the grid injection energy. This large negative dectrostatic potential, main¬ tained by continuous dectron injection (to make up losses) could then be used to trap positive ions in the system. Ions "dropped" into such a potential wdl would acquire energy at the "bottom" of the weU (i. e. , at the sphere center) equal to the negative potential established by the dectron injection energy. This scheme obviously depends on the conversion of kinetic energy of injected dectrons to negative electric potential fidds and is thus an inertial-dectrostatic method of plasma confinement. No means were provided to inhibit electron loss at the sphere surface. Somewhat later it was shown that such a negative potentid weU system is unstable to various perturbations if the confined ion density exceeds a certain level. H.P . Furth, "Prevalent InstabUity of Nonthermd Plasma" , Phys. Fluids , Vol. 6 , No. 1, pp. 48-53 (January 1963) . This level was shown to be so low that the system was not of practical interest. Furth agreed with Elmore et al that the system would be unstable, and further showed that such self- confined inertial dectron/ion systems using electrostatic confinement were inherently unstable. That is, systems in which confining non- equilibrium dectrostatic fields are to be produced by inertial- electrostatic conversion of one charged component would be unstable above some critical density of the other component. For con- finement by electron injection the ion density limit is too small to be of interest. Another system for electrostatic confinement of plasmas is set forth in U.S . Patents Nos. 3, 258 ,402 (June 28 , 1966) and 3, 386,883 (June 4, 1968) to P .T . Farnsworth. FoUowing his approach further research has been conducted into the feasibility of electrostatic confinement of ions. See, e.g. , Robert L . Hirsch, "Inertid-Electrostatic Confinement of Ionized Fusion Gases" , Jour. Appl. Phys, Vol. 38, No. 11 (October 1967) . Hirsch also utilized conversion of inertid energy for the production of centrd electrostatic fields. His work foUowed dong the lines developed by Farnsworth. (above) , and utilized spherical grid structures and geometries as. outlined in his U.S . Patents Nos. 3, 530, 036 and 3, 530,497 (botlr September 22, 1970) . Hirsch used injected ions (of D and T) rather than electrons. The severd-thousand-fold mass difference (ions heavier than dectrons) aUowed the attainment of much more stable fidd/ion structures than predicted for dectron injection, and the devices tested by Hirsch achieved fusion reaction rates in excess of 1.0E10 reactions/second on a continuous basis. However, the geometry which was used was not completdy spherical; the ions were injected by six opposing ion guns mounted in opposite cubic- faced array. Later andysis suggests that this geometry as weU as other conditions of the experiment caused intersecting beam phenomena and ion/gas collisions to dominate over other phenomenoiogies important to dectrostatic confinement, as these were envisioned by Farnsworth and Hirsch in their earlier work. D.C. Baxter and G. W. Stuart, "The Effect of Charge Exchange and Ionization in Electrostatic Confinement Devices" , Jour. Appl. Phys. , Vol. 53, No. 7, pp. 4597-4601 (Jdy 1982) . In par¬ ticular, it appears that current amplification by mdtiple transits across the potentid cavity did occur, with consequent beam buUdup, in part due to reflection of ions by the grid structures opposing their own injector structures, as indicated by the sensitivity of neutron output to injection beam dignment. Here (as in the work of Elmore et d) no mechanism was invoked to provide any other confinement of electrons at the surface or periphery of the approximatdy- sphericd system geometry. The use of electron injection to produce negative plasma potentials for enhanced confinement in magnetic systems was exa¬ mined in Soviet work on magnetic mirror systems. Work of the Soviet group at Kharkov, as reported in the Annals of the New York Academy of Sciences, Vol. 251, the proceedings of a conference held March 5-7 , 1974 on Electrostatic and Electromagnetic Confinement of Plasmas and the Phenomenology of Rdativistic Electron Beams, (L.C. MarshaU and H .L ; Sahlin, ed. , 1975) . These systems used physical ring electrodes in the ring cusp region of bi-conic cus systems to inhibit plasma ion losses, and employed axial electron injection in cylindricd geometry to enhance ion magne¬ tic confinement by producing negative potentials in the plasma region of this and of solenoidd Ioffe-bar-type mirror systems. Similar work by Blondin and Dolan invoked fixed cusp-region anode and cathode structures to dd magnetic cusp/miror plasma ion con¬ finement by the imposition of dectrostatic fidds in both the polar and equatorid loss cones. D.C. Blondin and T .J. Dolan, "Equilibrium Plasma Conditions in Ξlectrostaticdly Plugged Cusps and Mirrors" , J. Appl. Phys. , Vol. 47, No. 7, pp. 2903-2906 (Jdy 1976) . R. L . Hirsch had earlier studied this method to dd con¬ finement in solenoidd mirror magnetic confinement systems. U.S . Patent No. 3, 655, 508 (April 11, 1972) . Still other work utilized ion injection to establish positive potentid fidds in bi-conic or mirror cusp geometries, or in twisted bi-conic mirrors used as "plugs" at the ends of linear solenoids (See, e.g. , F .L . Hinton and M .N . Rosenbluth, "Stabilization of Axisymmetric Mirror Plasmas by Energetic Ion Injection" , Nucl. Fus. , Vol. 22, No. 12, pp. 1547-1557 (1982) , and P .J . Catto and J .B . Taylor, "Electrostatic Enhancement of Mirror Confinement" , Nucl. Fus. , Vol. 24, No. 2, PP 229-233 (1984) . ) AU of these approaches used fixed dectrodes and/ or ion or dectron injection to establish dectric potentids to aid magnetic plasma confinement systems, not for the direct electrostatic confinement of ions. In summary, previous work in inertid, magnetic, and electrostatic confinement dmed at the confinement of charged par- tides (ions) , for the purpose of creating conditions usefd for the generation of nuclear fusion reactions between them , has shown that: (1) Magnetic fields do not provide restoring forces to charged partides in motion, or to confine plasma partides; they provide deflecting forces, at right angles to the direction of motion of the partides. Electrostatic, electrodynamic, and other dectric fidds can provide direct restoring forces for the confinement of charged partides. (2) Even the most favorable magnetic confinement geometries lose charged partides by gyro guiding center shifting due to microscopic collisions between partides. Such collisions, are essentid for the creation of nuclear reactions. (3) Collisions between partides of like sign have the most effect on ion losses. Such collisiond losses are governed by the gyro radii of ion/ ion collisions in conventiond magnetic con¬ finement schemes. Electron gyro radii are very much less than those of- ions of comparable energy. .(4) Electron and ion motions in magnetic fidds are of opposite sign. This resdts in the dectric polarization of the plasma, with the establishment of an ambipolar didectric fidd. - Plasma losses are then set by the rate of ion/ion transport collisions across the fidd. (5) Inertid- electrostatic potentid wells established and mdntdned by charged partide injection done and held soldy within dectric fidd structures are stable ody for confinement at partide densities below a certdn criticd value. This is found to be too low for the production of nudear fusion reaction rates usefd for power generation. SUMMARY OF THE INVENTION Considering dl of these facts and features it appears that usefd confinement of plasmas can be achieved by an improvement on aU prior concepts, by new and unique uses and combinations of magnetic and electric fields, and by use of inertid forces. The current invention accomplishes this by: (a) Using a substantidly sphericd magnetic fidd geometry which is macroscopicdly and magnetohydrodynamicdly (MHD) stable for confinement of charged partides to confine a plasma which is non-neutrd with excess density of dectrons. This reqdres use of a magnetic fidd geometry which is everywhere con¬ vex towards its confined ion/ ectron/ lasma system. (b) Using a magnetic fidd geometry with minimum losses; e.g. , a "mirror" type system without line or ring cusps - its cusps are aU point cusps. The geometries of interest utilize spedd polyhedrd configurations for magnetic fidd generating means. OsciUation of single polyhedrd or mdtiply- faceted interlaced poly- " hedrd surface fidds may .be usefd to provide good magnetic sur¬ face "reflection" of confined dectrons, by causing the time-averaged fidds to appear "quasi-sphericd" over the dectron gyration time at the locd fidd strength. (c) Using the excess dectrons thus confined to pro¬ duce a centrd dectrostatic fidd which is stable (by virtue of stable electron confinement by the magnetic fidd) and in which the desired negative potentid can be mdntdned at any density of "trapped" ions (less than the totd density of dectrons) . (d) Injecting electrons at high energies (e.g. , 10 kev to more than 1 Mev, depending on the ions chosen for con¬ finement) into the stable magnetic configuration, to establish nega¬ tive potentid wells of depths suffident to confine ions at energies at which nudear fusion reactions will occur. (e) Adding ions to the system by injection, to attdn ion densities needed for usefd nudear fusion reaction rates, and to provide high pressure to support the centrd plasma core, by dynamic conversion of the energy of injected ions fdling into the confining potentid weU (e.g. , as by two-stream instabUity coupling of momen¬ tum from the in- falling ions to the core fidd structure) . It is the object of this invention to overcome the defects and defidencies of previous concepts for electrostatic confinement of ions by utilizing the confinement abflity of (MHD stable con- figurations) of magnetic fields for the confinement of electrons, so that stable electric fidds produced by their confined distribution in turn may be used to confine the ions. It is further the object of this invention to utilize these means for ion confinement to achieve densities of such confined ions at vdues large enough to aUow nuclear, fusion reactions to occur at usefd rates. It is further the object of this invention to provide a con¬ finement means for ions which can confine a variety of ions of interest for nuclear fusion, at partide energies up to the range of 400 kev to 2 Mev, as weU as at smdler ion partide energies. The. concepts of the current invention provide for a device able to ensure stable entrapment of positive ions which are injected into negative dectric fidd configurations capable of confining these positive partides. These dectric potentid configurations are formed by spatiaUy-stable distributions of dectrons from dectron injection into stable magnetic fidd configurations, to yidd net excess dectron (over ion) density, and thus net negative internd potentid distri¬ butions. These stable quasi-sphericd magnetic fidd configurations are aU point-cusp mirror fields, placed with dternating sign (or sen¬ se) on the surface planes of any of the regdar polyhedra when trun¬ cated (except for the octahedron untruncated; the octahedron is just a trunacated tetrahedron) ; or on any other arrangement of polygond faces on or extending from these surface planes, or forming any other ordered polyhedron. A feature of importance to optimd func- tio ng of the current invention is that the arrangement of polygond faces must be such that dl intersection points (between faces) are surrounded by an even number of faces. Another feature of impor¬ tance is the possible oscillation of the surface magnetic fidds at frequendes high enough so that good surface magnetic "reflection" is provided to the confined electrons. Ions may be injected with any energy from (nearly) zero up to (or greater than) that of the energy of injected electrons. Electrons may be injected with energies of 10 kev up to severd Mev, but must be injected with sufficient energy to establish centrd negative electric potentid wdls of greater depth (strength) than the energy level at which it is desired to promote or contdn ion- coUisiond interactions among the ions trapped in the negative poten¬ tid well. Increasing electron injection energy (voltage) may lead to negative potentid wdl depths great enough to initiate nudear fusion reactions between injected/ confined plasma ions of the light dements and their isotopes (e.g. , H , D , T, Li, B , Be, etc. ) . Increasing injection energy of the ions may likewise lead to such wells, through the mechamsm of "virtud electrodes" originaUy discussed by Hirsch and Farnsworth. Alternatively, some form of both effects may be used in the current " invention. In devices operated at conditions capable of creating nudear fusion reactions, the strength of the (surface) magnetic fidds and (internd) electric potentid fidds is such that: (a) fusion products wiU escape entirdy from the fidd regions; (b) unreacted ions wiU be trapped in the wdl by the electric fidds, and; (c) electrons wiU be trapped internaUy by the magnetic fidds. This is a resdt of the fact that the radii of gyration of charged partides in the magnetic fields of the device are much larger for fusion pro¬ ducts than the dimensions of the device, are comparable for trapped ions, and are much smaUer for dectrons. This feature is unique among aU other concepts for the confinement and generation of nudear fusion reactions. One consequence of this feature is that fusion reaction energy carried by fusion product ions is not deposited locdly in the entrapped plasma by collisions therewith but, rather, is carried out¬ side and away from the source region in which the reactions them¬ selves are caused to occur. Thus, fusion energy so created does not contribute to the "heating" of plasma ions, and the device of the current invention is not an "ignition" machine, nor does its func- tio ng depend upon "heating" a mass of plasma ions to a sufficiently large temperature to ensure significant fusion reactions, as is the case for dl other magnetic and/ or inertid confinement concepts for the attdnment of fusion. Electron and/ or ion injection may be steady-state (cw) or pdsed at frequencies from a few Hz to severd hundred MHz. This frequency may be made equd to the frequency of oscUlation of current flow in the magnetic fidd coils, if these are driven in an oscillatory mode. Such pulsing of the injection beam which is responsible for establishing the potentid wdl which confines the ions so that they will react among themsdves, wiU naturaUy cause the inter-iomc reactions to osdllate with the frequency of oscUlation of the weU induced by the injection pdsation. In such conditions the release- of energy from ion nudear coUisiond interactions will osdllate as wdl, and so wiU the output of (charged) colUsiond reaction products. When operated in such a pdsed or oscUlatory mode, nudear-reaction-generated energy may be coupled into osdllations of the confined plasma, itself, to yidd amplification of the pulsations and thus to yidd high frequency radiative power output, or to yidd oscillation of surface potentials on the contdner walls surrounding the plasma region, and thus to surface (sphericd) wave generation. By this means the device can become a sdf- amplifying, sdf-powered generator of microwave or other radio-frequency energy. If operated with electron injection currents, ion densities, and magnetic fidds which aUow large power gdn to occur, such a device can be used as a powerfd source of radio- frequency energy, for radar, com¬ munications, power- beaming, energy beam weapons, etc. , with no externd source of mdn power. At the onset of fusion reactions in the device, the fusion product ions wiU escape from the system, leaving behind their dectrons, to yidd a still- more-negative confining weU. This eodd lead to a "runaway" effect in which contindng reactions yidding fusion products create an ever-deepe ng well, which in turn increases the fusion rate, which deepens the weU more, etc. This process wiU be stopped by burnout of the ion fuel in the wdl, by arcing or other "shorting" or destabilizing effects, or by reaching stable burn conditions in balance with the ion and electron injection rate, and the rate of escape of electrons and of ions from the sur- face of the confinement region (i. e. , from the magnetic fidd) . The nature of this sdf-initiated creation of deeper potentid wells wiU depend upon the species of ions used in the device, and undergoing fusion reactions. If dl the ions involved carry ody single nudear charges (i. e. , if dl have ody one proton in the nudeus) , then the onset of fusion reactions can lead to a weU-deepe ng effect, as described above, ody for a limited transient period. This transient wiU be damped out by the continuous injection of new electrons and ions, to reach a new stable density distribution. However, if the ions involved carry more than one proton in their nudeus and are injected ody partiaUy stripped, with a single charge, then the onset of fusion will trigger an exponentid wdl-deepemng process stabUizing at a new, deeper wdl depth as a resdt of each fusion reaction leaving more dectrons behind in the weU than were originaUy injected. Partide injection (ion or dectron) may be dong the magnetic cusp fidd axes, or offset but paraUd to them , or in an anndar sheath around these axes. If anndar, the partide sheath may be injected with or without rotation; if offset-axid or on-axis the partide beam may be injected with or without rotationd or nutationd motions. If rotation/ nutation is used in the injection pro¬ cess, this will have the effect of preventing the partides from "fdling" directly radidly inward into the potentid wdl, towards zero radius. Rather, such partides wUl be constrdned to converge to a mmimum radius greater than zero on account of the angdar momentum they possess by virtue of the rotationd momentum with which they were injected. The beneficid effect of such angdar momentum on stabUization of the confuting potentid well has been shown by experiment. J. T. Verdeyen, et d, "Recent Developments in Electrostatic Confinement - Experimentd" , Ann, of the N .Y. Acad. of Sci. , Vol. 251, May 8 , 1975. In these experi¬ ments it was dso shown that the introduction of angdar momentum resdts in formation of a "virtud" centrd dectrode of smdl radius, and in the reduction of weU depth and mdntenance of parabolic shape of the well. Ions also may be injected in pardlel with electrons (anndar and axid beams) or opposing the dectrons (opposite magnetic cusp faces on the polyhedrd configuration (used) , or in opposing each other, or in paraUd with ions, or in any other fashion recognized to be appropriate by one of ordinary skUl in the art. Fusion reaction products * wiU generdly escape regions con- tdrang the plasma, dectrostatic fidds, and dectrons, and be depo¬ sited in and on structures around but outside of these regions. Since these . products are dl positively charged and carry high energy (severd Mev each) their energy may be converted directly to electricd energy in externd drc ts by causing the externd struc¬ tures (on which the fusion products impinge) to operate at high positive electric potentials (voltages). With such an arrangement the positively-charged fusion products must escape "up hill" agdnst the applied positive potentials, and can drive dectricd energy into any circdt to which the externd structures are connected and which doses back to the plasma/ dectron/ weU region. The pressure of partides in the weU will be supported by the externd magnetic fidd which confines the dectrons, through the inertid effects of conversion of the kinetic energy of in-faUing ions to electrostatic dynamic pressure on ions confined in (but moving outward from) the centrd core of the potentid wdl reacting volume. This wdl itsdf is produced by the conversion of the iner¬ tid energy of injected electrons to the energy of the weU depth at the electrostatic potentals established by the stably-confined dectron density. This electrostatic weU gives energy to the in-fdling ions, which in turn couple their thus-acqdred energy of motion (and momentum) into confinement pressure on the core. The kinetic energy of injected dectrons thus, through the medium of the electrostatic well, is transformed into the kinetic energy of in-fdling ions. The ratio of momenta of ions and electrons of the same energy is given by the square root of the ratio of their masses, thus this transformation has the effect of producing an iomc "gas" whose (dynamic) pressure is very much larger than the equivdent (dynamic) pressure of the injected dectrons. In addition, the con¬ vergence of the quasi-sphericd geometry of the polyhedrd con¬ figurations of interest increases the locd dynamic pressure by the square of the inverse ratio of radii from the outer (electron injec- tion) radius to the inner (ion dynamic pressure confinement) radius. As an example of these ' effects, if the ions are those of deuterium (D = H2) and the radius of the inner core is 0.1 that of the inner "surface" of the confinement fidd region, then the ratio of ion-generated pressure on the core to dectron pressure on the (externd) confimng fidd will be roughly 6100 :1. The physics phe¬ nomena invoked in this invention thus have the effect of creating an electricd "gas" inside the magnetic fidd region whose (dynamic) pressure at large radii is very much less than its pressure at smdl radii within the volume which it occupies. For this reason, it is possible to contdn and confine a high density of reactive ions in a smaU radius within a larger radius at which a relatively weak magnetic fidd is placed; it is not necessary for the magnetic fidd to provide the confimng pressure over a large radius to hold the high density plasma together " at the pressure at which it operates within the smdler radius core. For example, ion densities of 1.0E15 to 1.0E17 per em 3 may be sustdned in D at 100 kev with surface magnetic fidds of ody 1 to JO kG (kUogauss) . The coupling of in-fdling momentum of the ions to ions from the core wiU be accomplished by mdti-stream instabUity interactions, through quasi-sphericd waves. In this the partides streaming inward and outward through each other wiU interact coUectively, above some ion current density, through the generation of electrostatic waves which transfer momentum (and energy) from one stream to the other and operate over very short interaction distances (wavelengths) . There wiU dways exist a radius suf- fidently close to the center at which the convergent density becomes large enough to initiate dectrostatic wave instabUity interaction, hence this phenomena will dways be avaUable to provide dynamic pressure coupling to the core region. Note that scattering collisions in this geometry do not directly increase partide losses, because they occur near the center and their effect of changing the direction of motion still leaves aU motion predominantly radid in vector direction. It is important to note that requirements on ion beam injection power are minimd in an dectron- injection-driven device, since most of the ion energy is aeqwred by "fdling" down into the negative electric potentid wdl set up by the dectron injection. This potentid wdl depth is established by the net excess dectron density which is set up over the ion density contdned therein. This is limited by the loss rate of electrons from the surface region of the polyhedral magnetic fidd configuration. Higher fidds give smaUer loss rates; larger injection currents aUow larger losses. Thus, the balance between losses and input wiU set the level of excess dectron density. Numerical cdcdations show that ody modest dectron injection powers are reqdred with modest fidds (as above) to yidd very deep electrostatic wells for ion confinement (e.g. , over 200 kev) . The power output is set by the rate of reaction within the centrd region, integrated over the volume of this region. The reaction rate is determined by the square of the ion density (and the product of reaction cross-section and partide speed) , thus is Umited by the ion current density in the centrd region. In-faUing ions wiU converge as the inverse square of the radius, thus the reaction rate will tend to vary as the inverse fourth power of the radius. This very rapid dependence ensures that nearly dl of the fusion energy generated in such a device will be generated in and around the center of the (structurdly-empty) cavity confined by the externd magnetic fidd, at the largest possible distance from the walls of the system. It will be somewhat like a little "star" burmng in the center of the electrostatic weU cavity "void" . Numericd cdcdations show that the ion current densities required for totd fusion power output at "usefd" levels is much larger than those required for power bdance makeup agdnst dectron losses, or for pressure support of the reaction core. To achieve this state requires a current mdtiplication or "gdn" (Gj) achieved by the recircdation of ion (and dectron) currents across the machine volume many times, until a sufficient ion density is achieved. The reqdred current recircdation factor is found to vary roughly as the inverse fifth power of the major radius (R) of the device, so that 5 Gj — (1/R 5 ) . Large devices thus wiU require less current "gdn" than smaU devices, and it is dear that there must exist a size suf- fidently large that the "gdn" may be unity (Gj = 1) , and that no current mdtiplication is reqdred for operation of the machine at a breakeven power balance. Numericd cdcdations show that this size 10 is approximately R — 10-20 m, and that Gj — 1..0E5 will a ow R — 20-30 cm (Gj vdues greater than 1.0E6 have been obtdned in a variety of dectron and ion magnetron tubes of other types) . Another feature of the device is the existence of a "black hole effect" (BHE) in respect to fusion burn reactions. This resdts 15 from the fact that there must exist a radius at which the fusion reaction collision rate is sufficiently large that the totd fusion reac¬ tions occuring per unit volume over the time of flight of an ion from this radius to the center of the machine wodd equd or exceed the totd density of ions at this radius. For such a condition it is dear 20 that dl ions entering- (i.e. , fdling into) this radius region wUl undergo fusion reactions. BRIEF DESCRIPTION OF THE DRAWINGS These and other aspects of the invention will become more clearly understood from the following description read together with 25 the drawings, in which: Figs. 1A and IB are diagrams showing the magnetic force lines for a conventiond simple bi-comc magnetic mirror plasma confinement device as described above; Fig. 1C is a diagram iUustrating reflection of a 30. moving charged partide at a point cusp, described above; Fig. 2 is a diagram of a known polyhedrd devices for confining plasma, described above; Fig. 3 is a diagram showing a known arrangement for electrostatic confinement of dectrons, described above; Fig. 4 is a diagram showing direction of current flow in an octahedrd magnetic field generating and electron confining device according to the present invention; Fig. 5A is a partiaUy schematic perspective of a single turn of a magnetic coil for face 410 of the octahedrd magne¬ tic field generating device depicted in Fig. 4, and Fig. 5B is a schematic view of a mdtiple turn coil for the same face; Fig. 6 is a partiaUy cutaway and schematic view of a potentid weU and partide concentrations in an octahedrd device according to the present invention. Fig. 7A is a cross-sectiond graph and Fig. 7B a plan view of the potentid weU and ion concentrations in the present invention; Fig. 8 is a diagram showing a current flow pattern in a truncated cube configuration of an ion confinement device according to the present invention; Fig. 9 is a diagram showing one possible arrangement for ion and electron injection into a truncated cube embodiment of the present invention; Fig. 10 A is a diagram showing a cross-sectiond view of the embodiment of Fig. 9 taken dong X-X and arranged as it might be arranged to serve as a heat-generating and therm d/ electricd conversion element of a power plant, and Fig. 10B shows a direct-electricd conversion element; Fig. 11 is a graph showing the current amplification (Gj) required fora range of overaU power gain (G) of the device as a function of size (R) , for severd charged particle reaction possi- bUities, and shows the conditions needed for attdnment of the "black hole effect" , described above; Fig. 12 is a diagram of a structure resdting from superposition of an octahedron and a truncated cube; and Fig. 13 is a graph iUustrating the concept of periodic variation in the depth of the potentid weU as it might be practiced in conjunction with the present invention. DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS It is the object of this invention to achieve large ion den¬ sities in stably-confined plasmas, hdd in negative dectric potentid wdls formed by magneticdly-confined dectrons. This is to be done by the means described below. Electrons are injected dong the fidd lines surrounding and entering the centrd (confined-plasma) volume. Injection is through point/polar magnetic cusps in an inherently confinement-stable magne¬ tic mirror fidd system with minimum loss properties. "Such systems are attdned in the present invention by use of various polyhedrd magnetic cusp confinement geometries using tetrahedrd, octahedrd, and/ or dodecahedrd configurations. Udike the bi-comc mirror systems, such configurations have the property that coil windings may be made dong their faces in such a way that no ring or line cusps are generated in the magnetic field geometry, aU magnetic loss cones are through point or "polar" cusps, ody. The geometries preferred for this system are dl of the regdar polyhedra truncated on each point, except the octahedron, which may be used without truncation (it is dready the truncation of the tetrahedron) . Any other polyhedron in which dl the magnetic ver¬ tices are surrounded by an even number of polyhedron faces may be used as weU. For such figures the magnetic fidd point cusps (or "magnetic poles" ) are to be centered on each face of the pdy- hedron, in an dternating pattern, so that no two adjacent faces contdn cusps of Uke sign. The criterion for this is simply that dl vertices be surrounded by an even number of polyhedron faces. Figure 4 shows possible current paths for such a cusp fidd arrange¬ ment for the octahedron, and Figure 8 shows this for the truncated cube. It shodd be noted that opposing faces of such polyhedra dl lead to bi-comc mirror fidds of opposing sign, except for the trun¬ cated tetrahedron (the octahedron) , in which the opposing fidds are of Uke sign. The octahedron thus is equivdent to a four- fold intersection of mirror-cusp-ended solenoidd fields, in which each mirror cusp provides stabilization for its adjoimng solenoidd fidd regions. The overdl geometry of the rdevant magnetic fidd w l be referred to herein as "substantidly sphericd" or "quasi-sphericd. " Attention wiU now be focussed on an octahedrd system, starting with Fig. 4. As mentioned, the octahedron 400 depicted therein has current flowing dong its edges to establish a magnetic fidd exhibiting point cusps on each face 410. The signs of the point cusps dternate between adjacent faces. One possible current flow pattern is depicted by the solid arrowheads shown in the drawing. Figure 5A shows one of the current carrying elements 500 used to generate the magnetic fidd. Current carrying dement 500 is supplied with current from a power source 510. This power source codd be d.c. as in 510 or a.c. as in 515. Fig. 5B shows a typicd mdtiple turn current-carrying coU for the same polyhedrd face. It shodd be mentioned that each face 410 codd con¬ ceivably be provided with a linear permanent magnet dements to generate the desired fidd configuration. Figure 6 Ulustrates dectric fidd and partide density distributions during operation of octahedrd magnetic fidd generating or plasma confinement device 400. Details concermng the generation and configuration of the magnetic fidd are omitted for darity. The electron and ion injectors used respectively to establish the negative weU and "spUl" ions into the weU wiU be set forth in greater detdl below in connection with the truncated cube system. As depicted in Figure 6, dectrons injected into the octa¬ hedrd magnetic fidd source become trapped by the magnetic fidd to form a substantiaUy sphericd negative potentid wdl 600. The pro- babUity of locating an dectron increases toward the center of the negative potentid weU. Electrons are originaUy injected to establish the negative potentid wdl 600 and then continuously injected thereafter to sustdn the negative potentid wdl 600. Synonyms for negative potentid wdl wodd indude virtud cathode or negative space charge. Once the negative potentid well 600 is established, positive ions are injected into it at rdatively low energies. The positive ions "fdl" into the well, then increase in kinetic energy as they are drawn toward the center. The charged partides osciUate across the potentid wdl. As the ions cross the center, they encounter and interact with other ions. It is anticipated that attdnable plasma temperatures and confinement times wiU meet or exceed the thresholds required for usefd levels of fusion reactions, in which fusion power generation is significant. This is depicted in Fig. 6 as a centrd region of maximum coUision density 620. This collision density varies idedly as the inverse fourth power of the radius, and so is highly peaked at the center of the sphericd wdl, dthough practicd considerations prevent it from reaching near-infimte density as r approaches zero. The negative potentid wdl 600 is dso depicted graphicdly in Figs. 7A and 7B. The diameter of the wdl is designated 2R. The "depth" -V corresponds to the voltage used to accelerate the electrons for injection into the cavity. Quditative density distribu¬ tions are dso depicted for the "ided" case and the "practicd" case. Alternatively, ions may be injected to form a positive "virtud (anode) electrode" in the device center as described by Farnsworth and Hirsch, with dectron injection in addition towards and through this virtud dectrode, to form an ion-confimng negative potentid wdl within the ion- formed virtud anode. In either case ions wiU be trapped by negative potentid wdls which are, in fina¬ lity, held in place stably by circdating dectron currents tied to stable externd magnetic fidds of an appropriate polyhedrd geometry which ensures low dectron losses and ease of injection of dectrons and ions into the system. Inertid energy and momentum content of either or both the electron and/ or ion injection beams can be utUized to provide compressiond pressure forces to sustdn high pressures in the centrd plasma core of the device. The conversion of inertid energy con¬ tent of injected charged partides can be accomplished in the centrd (convergence) region by simple (Codombic) collisiond means (which may involve the generation of mdti-stream instability interactions) , or in the (surface) magnetic fidd regions by interaction through gyration on orbits on which the partides (particdarly the dectrons) are trapped when injected in an anndar fashion, par did to the cusp field lines. System power bdance constrdnts arising from pressure bdance considerations may limit the maximum gdn (G) attdnable in the system. More detaUed consideration of this issue is given below, in connection with a summary of physics phenomena which are of importance in the operation of such systems. Figure 8 depicts a truncated cube system 800. A possible pattern for current paths dong the edges is shown using smaU solid arrowheads.. Eig. 9 provides details of dectron and ion injection. In: the. polyhedrd systems of interest here dectrons may be injected either directly dong a cusp axis (or axes) or in an anndus around such axis/ axes. If injected in an anndus, they may be injected either with paraxid velodty (dong the locd cusp fidd lines) or with a rotationd component around the cusp centrd axis. A negative potentid wdl is thus formed by the injected dectrons converging to and trapped within the centrd region of the externaUy-driven magnetic fidd system. Ions are injected to be trapped in this negative potentid wdl. These may be injected coaxiaUy with the dectrons, in an anndus surrounding the dectron beam, with or without ion beam rotation, or in a centrd axid beam within an anndar dectron injection beam, or may be injected through magnetic point cusps on faces of the polyhedrd system opposing the electron injectors. In Figure 9, numerd 900 designates a first positive ion injector. First positive ion injector 900 indudes a gas idet 910, an iomzing region 915, an accelerating grid 920 and an anndar beam lens 930. Thus, first positive ion injector 900 is constructed and arranged to produce an anndar beam centered on one of the axes of the truncated cube system. Numerd 940 designates a first dectron injector. First electron injector 940 is dso centered on an axis of the truncated cube, and is constructed and arranged to direct an anndar dectron beam to the center of the interior volume of the truncated cube. First dectron injector 940 indudes an electron emitter 950 electri- caUy connected to an emitter power source 955, and an accelerating grid 960. This grid is held at an electric potentid +V above that of the emitter, by an dectron grid power source 965, thus producing a centrd potentid wdl depth of -V (Fig. 7A) . Additiond injectors, may also be provided. Fig. 9 illustrates the provision of an additiond injector of each type, a second positive ion injector 970 arranged symmetrically opposed to the first positive ion injector 900, and a second dectron injector 980 arranged symmetrically opposed to the first dectron injector 940. The detatts of construction of these additiond injectors wiU in generd be the same as that of the opposed injector of the same type. Thus, these details have been omitted from the drawing for clarity and wiU not be further discussed here. Details for injector placement on the surface of an octa- hedrd system are substantiaUy the same. Figure 10A illustrates one possible arrangement for the truncated cube system of Fig. 9 as a heat-generating element in a power plant. Truncated cube dectron confiner 800 is shown in a cross-section taken dong Une X-X of Fig. 9. The system is placed with its assodated injectors 900, 940, 970, and 980 in an evacuated contdnment structure 1000, depicted as a drcdar sheU. As shown in Fig. 10A, contdnment structure 1000 is heated by absorption of radiation 1100, and by collisions with partides 1200, generated by the fusion reaction occurring in truncated cube region 800. This heat is thermaUy coupled to a heat exchanger 1020 (section of heat exchanger shown) in which a working fidd such as water absorbs heat. The heated water is then conveyed through thermd to electric conversion unit 1010 which converts the heat energy stored in the water into dectricd energy. Thermd to electric conversion unit 1010 may be any known means for converting heat energy into electridty. Fig. 10B shows one arrangement for direct dectricd conversion of fusion product partide 1200 energy by causing the par¬ tides to travel outward agdnst a positive dectricd bias fVp applied to the contdmng sheU 1000. The contdnment structure 1000 is evacuated through eon- ddt 1030. The truncated cube electron confinement device 800 is cooled via cooling channd 1040. The physics phenomena which control the action of such systems allow operation over a very wide range of sizes, from a few centimeters in confinement volume radius to many meters for such a dimension. Electron surface losses through and from the confining magnetic fidd will Umit the power bdance performance (i. e. , the system power gain) of such devices. However, a simple estimate of maximum potentid system gain can be obtdned by balancing electron injection requirements with ion makeup needs to replace ions burned up by fusion reactions in the confined core. This method ignores surface losses, and limits dectron power needs to internd reqdre- ments, ody. If scaling of the fusion power is constrdned by limiting energy flux through the boundaries of the device, then it is possible to cdcdate a maximum upper Umiting system gdn vdue (G+) for any size of machine. Although unrea sticaUy optimistic from an engineering standpoint, the resdts of such an andysis show absolute upper limits on system power gdn. These (G+) vdues vary roughly linearly with system radius (R) . The size of such devices can range from R = 10 cm radius to a radius of severd meters (e.g. , R = 3 m ) . Some crude estimates of these parameters are given in Table 1, for systems operating on DT or DD fusions. The upper limit system gdns possible for use of other fuels and nudear reactions wUl be less than those shown, because operation with such fuels wiU require larger negative electric potentials than for DT/DD. The indusion of redistic externd loss effects, and the requirements for beam injec¬ tion to support centrd plasma core pressures wiU yield considerably lower practicd gain vdues from such machines. TABLE 1 ELECTRONΛON BURN BALANCE LIMIT ON POTENTIAL RANGE OF DT/DD SYSTEM PERFORMANCE B-FIELD REACTION DRIVING UPPER LIMIT SURFACE POWER POWER SYSTEM POWER RADIUS OUTPUT (1) INPUT (2) GAIN ( 3) (R) (Pf, Mw) (Pi, kw) G+ = Pf/Pi 10 cm 0.1-1 2.5-25 4- 40 30 cm 1-10 8-80 12- 125 1 m 10-100 25-250 40- 400 3 m 100-1000 80-800 125-1250 (1) surface energy flux at radius R is 0.08-08 kw/cm 2 (2) negative dectric potentid wdl is about 100-200 kev (3) system power gdn may saturate at about G < 1000 The smallest size of practicd interest is that at which the dimensions of the confimng magnetic fidd volume are comparable to or less than 10-100 times those of the radius of gyration (gyro radius) of dectrons at given energy in the confimng fidd at the periphery (surface) of the confined volume. Devices smdler than this wiU be dominated by losses of dectrons out through the loss cones of the polyhedrd field systems. Typically, gyro radii of 0.5mm-5 mm characterize electrons at transverse energies of about 20-50 kev in magnetic fields of 1-5 kUogauss. Thus, dectrostati- caUy confined plasma systems of this type whose confinement volume radii are much smaller than about 10 cm will suffer from greater relative electron losses than wiU larger systems. Devices smdler than this wUl be dominated by higher relative power needs (than for larger systems) for cusp field magnets, and for requirements of centrd core pressure balance, rather than by electron losses due to injection requirements for surface loss makeup to mdntdn negative potentid wdl generation capabUity. These latter power losses wiU dominate the red power bdance gdn in larger devices. Their assessment can be made using electron transport coeffidents from previous work in fusion plasma physics. Jacobsen et d have anlayzed electron and ion losses in tokamak devices using essentidly dl of the models for dectron transport scding laws which are in current use in fusion research work. Robert A. Jacobsen, Carl E . Wagner, and Richard E . Covert, "System Studies of * High-Fidd Tokamak Ignition Experiments" , J. of Fusion Energy, Vol. 3, No. 4 (1983) . Electron losses through the cusp loss cones can be minimized by appropriate injection/ grid structures, geometries, and potentials. However, coUisiona losses of dectrons within the peripherd region of magnetic fidd surrounding: the centrd plasma are an unavoidable resdt of the need for significant surface electron densities to mdntdn the nega¬ tive electric potentid weU required to confine ions at usefd den¬ sities within the magnetic fidd structure. This surface collisiond electron loss rate sets the mimmum input power level of red devi- ces, and hence limits their power gdn. The power density of operation is given by the product of ion density squared and the fusion cross-section product with the ion speed within the weU. Since both the speed and cross-section increase with increasing w l depth (in the range of interest here) the power density wiU be determined (strongly) by the depth of the confimng electrostatic weU in the centrd plasma region. Larger weU depth wiU lead to larger power density for the partide reaction power. If this power output is limited to yidd a constant surface flux of energy generated within the system, the required confining weU depth wUl become smdler as the device size is made larger. The ion density which can be sustdned in such a system wiU be limited by the abUity of the fidds (both dectric and mag¬ netic) of the confinement system to support the pressure required by the ion density at the temperature of operation (i. e. , at the "temperature" of partides at the energy of the weU depth) . The kinetic pressure p=nkT of the plasma must be bdanced by an exter¬ nd pressure force to sustdn it stably. As often pointed out, the electric fidd (E) reqdred to "hold" a plasma ion density (i. e. , by fi E**2/8 H = nkT) sufficiently large to yidd usefd fusion power density does not seem practicdly attdnable. See, e. g. , S . Glasstone and R.H . Lovberg, Controlled Thermonuclear Reactions , D. Van Nostrand Co. Inc. , Princeton, 1960, Sect. 3.13. Here β is the "efficiency" of use of field energy density to sustdn par¬ tide energy density. SimUarly, for magnetic confinement (e. g. , by 6B 2 /8 H = nkT) either the volumes are so large or the magnetic coU currents are so large that net power bdances appear questionable. In the device concept and invention ddmed herein these limits are overcome by the use of the circdating electron and ion current, through the confining electrostatic potentid wdl region, as the means to couple momentum pressure support from a high pressure centrd core to a low pressure externd surface. In effect the drcdating or oscillatory centraUy-convergent currents act as a specid type of "gas" which exhibits a strong radid pressure gradient such that its pressure is very large at the center and small at the periphery of the dectrostatic wdl region. Andysis of the current requirements for pressure bdance shows that the net system gdn G (for given surface injection current density) is rdated to the cavity current amplification factor Gj and the system characteristic radius by G = Cl (R**5) (Gj** 2 ) . The coeffident Cl is found to be approximately Cl = 3.0E-17/cm5 for R in cm. For a "break-even" system , G = 1 , and a current amplification of Gj - 1.0E5 is reqdred for a system radius of R = 20 cm . Conversdy, without any current amplification at aU in the system , Gj = 1 , and G = 1 wUl be attdned at a system radius of R = 2000 cm = 20 rn. Amplification factors of 1E6 and higher have been attdned in a variety of dectromc high power tube devices. Figure 11 shows the current amplification factor Gj reqdred for a range of net system gain 1 < G < 100 for two reactive charged partide fuels, as a func- tion of system size, R. Also shown are the conditions required for attdnment of the BHE ("black-hole-effect" ) previously described. Another physics feature of importance in system operation is that the fusion products wUl, in generd, not deposit their energy in the plasma region (as is the case in "conventiond" concepts for fusion) , but will escape from this region to the structures and sur- faces bounding the polyhedrd magnetic/ plasma system . In this escape, these partides wUl leave as positively charged ions, thus increasing the net negative potentid of the plasma region. Each fusion event wUl cause an increase in the weU depth which is con- fining the reacting ions, hence will cause an increase in the partide density and resdting inter-partide reaction rate which wiU, in turn, cause a further increase in the negative potentid, the weU depth, etc. , etc. The onset of fusion reactions in a negative potentid wdl of the type contemplated herdn wiU thus imtiate a self-generating process to increase . the weU depth and thus to increase the fusion rate. Under certdn specid conditions (of totd recircdating ion current) it is possible, but not certdn, that - once started - a reacting assemblage of this type codd become sdf-sustdmng without any further excess externd dectron injection, beyond that needed for bdance with the ion injection rate itsdf. In any case, this self-generating-weU effect might aUow the reduction of dectron injection for wdl sustenance, and thus codd resdt in a reduction in the externally-supplied power required to drive the dectron injection - system. For systems in which the dectron-injection-generated wdl depth is kept the same for aU system sizes (i. e. , ignoring the scding of mid mum reqdred weU depth with system size, discussed previously, and ignoring the potentid reduction in dectron driving power which may resdt from self-generating wdls, discussed above) it is possible to estimate the electron surface leakage power losses by use of the standard coefficients (mentioned above) for dectron transport. Alternatively, electron surface losses can be estimated by use of the standard equations for dectron thermd conduction transport across magnetic fidds. D.L. Book, 1980 Revised NRL Plasma Formdary, Office of Navd Research, Wash. , D.C. The loss rate of electrons will depend on the current amplification which is extant in the machine at the conditions of operation. Since this is set by pressure bdance requirements, its choice is tied to the fusion reaction power output desired from the system. Andysis shows that the surface power loss due to dectron collisiond escape through the confimng polyhedrd field structures is set entirdy by the locd dectron density in the surface field region, not by the injec¬ tion current. For this reason, nearly any electron current mdtipli¬ cation is possible; however, the system power bdance - and 5 therefore its gain - wUl be fixed * by this surface loss rate, rather than by the dectron injection needed to make up for fusion-reacted ion burnup, used as the basis of Table 1. Andysis of such losses shows that the energy flux (Pe watts/ cm 2 ) of dectrons escaping through the surface fidd region is just: Pe = C2 (n 2 /B) where n Q is dectron density in dectrons/ cm 3 , and B is the surface layer fidd strength, in Gauss. With this, it is found that losses can be limited to 1 - 25 watts/cm 2 with modest fidds, whUe retdmng electron densities large enough to ensure current amplification vdues of about 1.0E5 < Gj < 1.0E6, and larger. 5 Operation of the system concept herdn has been discussed as though dways in a steady-state mode. This is not necessarily the ody way in which such systems may function. In particdar, once a centrd dectrostatic potentid wdl is established, and ions are trapped therein, it may prove possible - and usefd - to pulse the 0 well to stiU greater depth by the rapid injection of energetic electrons (e.g. , as from an dectron accelerator) into the confined ion region. By this means it may prove possible to ignite a fusion- burmng plasma within a potentid wdl which then becomes sdf- sustdmng, as discussed previously. 5 Another area in which osdllatory or dynamic effects may affect system performance is related to the effects of the geometric structure of the surface- confimng magnetic fidds on the shape and depth of the dectron-generated internd negative potentid wdl. Consider a magnetic fidd geometry, for example, in which the Q electron-reflecting fidd surfaces are planar in a cubicd array. In this (unredistic and undesireable) geometry injected electrons wiU never focus within the system and thus can never produce a negative potentid wdl in the center of the cube. Rather, the potentid wdl will tend to be uniform and the same everywhere, for dectron injection with uniform current density over each surface. In contrast, dectrons injected with i iform surface current density into a perfect sphericd geometry will osdllate radiaUy across the sphere, and will reach much higher density at the sphere center than at its surface. This w l resdt in a deep centrd negative potentid wdl which can confine ions in the system. In the mdti-faceted polyhedrd magnetic fidd geometries of interest here for dectron confinement, the degree to which the confimng fidds appear sphericd or quasi-sphericd to the dectrons wiU depend upon- the fineness of surface structure, and the time- averaged fidd strength and direction "seen" by electrons transiting (being reflected by) the fidd. An dectron moving radiaUy outward from the w l center will encounter a fidd of increasing strength as it approaches the confinement volume boundary. Its energy of motion, and thus its radid speed will Ukewise increase as it "falls" back up the potentid hUl which has been created by its injection. By proper choice of a suffidently large surface magnetic fidd strength, the radius of gyration of such dectrons can be made smaU compared to the dimensions of the- system, and the dectrons wiU be "reflected" and returned to the system. The vector direction of their returned motion wUl depend upon the field angles seen by the electrons in or during the reflection/ turning process. If the magnetic fidds are mdntdned at constant levels (i.e. , dc current driven, or fixed permanent magnets), the fidd strengths and angles will not change, and the reflected electrons will "scatter" off the fidd surfaces with a certdn angdar dispersion or spread. This spread wiU dways resdt in a reduction of the wdl depth attdnable in such a system as compared with that in a perfect sphericd system. However, it is possible, in prindple, to cause the fidds to osdllate in such a manner that the dectrons wiU perceive a time-averaged fidd direction which more nearly approximates a sphere, whUe stiU retdmng the properties of MHD stabUity and low losses through point cusps. This can be done by utUizing two (or more) interlocking polyhedrd geometries, and moddating the fidds at a frequency sufficiently high that they oscillate through many cycles in one transit time of an dectron. This is depicted in Fig. 12, which shows a structure resdting from the superposition or interlocking of an octahedrd geometry with a truncated cube geometry. At such conditions, the electron wiU "see" the cycle- averaged fidd strength and direction of the interlocked polyhedrd system; and this can be made to approximate a sphere quite dosely. This is the generd approach used by KeUer and Jones (mentioned above) , who studied rf confinement and heating of neutrd plasmas in an rf-moddated octahedron interlocked with a truncated cube. In order to make this approach fuUy effective, the field vectors shodd have the same sign locally in each of the poly¬ hedrd structures as they proceed through each oscillation cycle, and their amplitudes interchange. Although this was not the case in the KeUer and Jones work, they still observed sphericd dectric potentid waves in their system. Electrons at the confined volume surface region wiU be moving at maximum radid speed, hence wiU have a very short time for gyration/ reflection in this region, given a field of suffident strength, as reqdred. To produce a quasi-sphericd effective fidd for such electrons requires field driving moddation at a frequency higher than this gyration frequency. Conversely, near the center of the weU where the magnetic field is small, the dectrons possess and the electrons possess very smaU energy of motion, and are moving at relatively slow speed, hence the fidd oscUlation frequency required for apparent quasi-sphericity is much lower than that required for electrons at the larger radii nearer the system surface/ boundary. In effect, the frequency of moddation will set the radius region at which effective quasi-sphericity wUl become effective to enhance electron confinement. As a find consideration, note that the degree of discrete¬ ness of even a constant strength (i.e. non-moddated) fidd structure seen by the electrons depends upon their radid position as weU. Near the surface field-generating-coil region the locd field strengths are large, and the topograpicd structure of the fidds wUl follow that of the mechanical current-carrying structures which produce them . Deeper into the system, at smaUer radii, the discreteness of structure becomes smoothed out, until even dc fidds appear nearly- sphericd at and around the center. The moddation of fidds, the choice of frequency, and the interlocking of polyhedra, as described above, are aU controllable by design, and avaUable to improve the confinement properties of the system. Also of potentid interest is the possibUity of moddating the dectron (and/ or ion) injection beams to produce a moddation of the internd potentid wdl depth, and thus of ion confinement and reaction rate. Fig. 13 graphicaUy Ulustrates the possibUity of making the weU depth osdllate. In the situation shown in Fig. 13, the wdl depth periodicaUy varies between -Vo+Vg and -VO-VE with time. Thus, the variation can be expressed as -(Vo+VE) (sin wt) , where w is the frequency of oscillation of the wdl depth. The degree of moddation of the confimng electrostatic potentid weU depth wUl depend upon the radid oscUlatory current amplification (Gj) . If this is large, a given moddation of input beam wiU yidd ody a smaU fluctuation in wdl depth, unless the moddation is ' locked to a transit time frequency of the partides oscillating in the weU. With such resonant locking, it may prove possible to achieve large weU fluctuations even with small moddation of input injection current. An eventud Umit on this behavior will be set by the loss of coherence in beam /plasma resonance due to scattering in the transits of the beam after injection. Conversdy, if Gj is smdl, the wdl depth and reaction rate can be caused to fluctuate directly over a considerable range. Such moddation of reaction rate can dso produce moddation of system electric radiative power output, both from plasma oscillations coupling within the centrd core region, and from the production of large osdllating potentids on surrounding or contdmng structures. Plasma core oscUlations may dso be stimdated by externaUy supplied radio frequency power through antennas radiating sphericd rf waves into the plasma region. Such rf moddation (at injection beam frequencies, or harmomcs thereof ) may prove usefd to enhance the oscUlatory output of a system which is driven ody by injection beam moddation. Any coupling of direct dectricd power generated by the plasma into such rf wave structures wodd dlow the device to function as a self-powered rf amplifier. These modes of operation are not necessary to the conception of the device as an invention in the art, but may be of interest ' as dternative or in addition to steady-state methods of operation. The invention discussed herein offers the abUity to create nudear fusion reactions in a wide variety of fuels. As discussed above, these range from the least-techmcaUy-demanding DT system , to the least complex and least costly DD ' system , to the radiation- free higher-Z fusion fuds (e.g. pBll, et d) . CivU/commercid applications wUl favor the use of DD systems for the production of low-cost steam. Cheap steam can be used in conventiond means for the generation of dectridty, desdination of sea water, production of synthetic chemicd fuels (e.g. dcohols, cod Uquef action, etc. ) , chemicd and materids processing, etc. Some exemplary reactions which may be feasible with the present invention proceed as follows. First, D and T can be made to yidd DT fusion reactions according to: (1) D + T — > He4 (3.52 Mev) + n (14.1 Mev) ; ( = 17.62 Mev) , and confinement of D done can be made to yidd (with equal probabUity) DD fusion reactions as: (2a) D + D — > He3 (0.82 Mev) + n (2.46 Mev) ; (Q = 3.28 Mev) (2b) D + D — > T (1.01 Mev) + p (3.02 Mev) ; ( = 4.03 Mev) The T produced (in Eq. 2b) will react according to Eq. (1) with the D in the plasma, jf the fusion product tritons (T) are contdned in the system. In generd, in the systems considered, most of the energetic (Mev+) fusion products will escape the con¬ fined plasma volume. The He3 produced (in Eq. 2a) will also react, if confined, by: (3) D + He3 — > He4 (3.67 Mev) + p (14.7 Mev) ; ( = 18.37 Mev) Other reactions of interest include: (4a) p + Be9 — > He4 (1.3 Mev) + Li6 (0.9 Mev) ; (Q = 2.2 Mev) (4b) p + Li6 — > He3 (2.3 Mev) + He4 (1.7 Mev); (Q = 4.0 Mev) (4c) p + Bll — > 3 He4; ( - 8.7 Mev) It is usefd to note that reactions (3) and <4a)- (4c) yidd ody charged partides as their fusion products. Thus they are radiation- free with respect to direct prenetrating radiation products (e.g. fast neutrons). Table 2, below, summarizes the range of negative dectric potentid wdl depths reqμired for the confinement of sufficient ions for usefd reaction rates of the above reactions, for monoenergetic ions, and for equUibrium MaxweUian energy distributions. TABLE 2 RANGE OF NEGATIVE ELECTRIC POTENTIAL NEGATIVE ELECTRIC POTENTIAL NUCLEAR FUSION WELL DEPTH REACTIONS Monoenergetic ions MaxweUian ions D + T 15 - 100 kev 10 - 200 kev D + D 30 - 200 kev 20 - 400 kev D + He3 50 - 350 kev 30 - 600 kev p + Be9; p + Li6 100 kev - 700 kev 60 kev - 1.2 Mev p + Bll 200 kev - 1.4 Mev 120 kev - 2.4 Mev DD systems do not reqdre the use of externdly-supplied T , and thus do not reqdre breeding blankets of Li (in which T is produced by n capture in Li6) , as do dosed-cycle DT systems. Systems operating on D done will generate a significant output of neutrons at moderate energy (about 2.5 Mev; see Eq. 2a) in the DD fusion process. However, if the T produced in the DD reaction mix (see Eq. 2b) is not contdned or burned within the plasma, no energetic 14 Mev neutrons will be produced and the radiation hazard will be less than (1/10) that of a DT system (see Eq. 1) for opera¬ tion at the same gross fusion power level. D (H2^ - s tne least costly fusion fuel except for p (HI) , which requires more expensive Bll or . Li6 to generate radiation-free power. This fact and its rdatively low radiation hazard potentid make it a good candidate for use in civU/commercid/industrid profit- making energy plants. In such energy plant use, it is contemplated that the fusion device wiU be suffidently smdl in size and low in cost that it can be - operated to destruction or end-of-life without on-line mdn- tenance, and may be removed, disposed of and replaced at such time. In this fashion, its in-plant application method resembles that of other compact fusion devices. See, for example, U.S . patent No. 4, 387, 193, issued to the present applicant. However, except for use of DT fuel, no Li blankets are needed, and the fusion unit to be removed and replaced here need be ody the magnetic coil system of the current invention, not necessarily induding its ion and electron injectors. Such removd and replacement is not u que to fusion plants; simUar exchange of power sources is made in jet drcraft whenever the turbojet engines reach thdr point of aUowable wear or end-of-life, and to dectric light bdbs which are replaced when they faU whUe the dectric power plant supplying electricity to their sockets continues to operate. As previously noted, DD fusion systems may produce energetic DT fusion neutrons (14.1 Mev) if the T produced in hdf of the DD fusion reactions (Eq. 2b) is captured and fed back into the plasma region to be burned. Since the DD process, in the invention discussed herein, does not reqdre T for its startup or its continuation, no breeding of T is necessary for such DT reactions in a DD system. Thus dl of these energetic neutrons, as weU as dl of those lower energy neutrons resdting from the other hdf (Eq.2a) of the DD fusion process, are avaUable to be used for the nudear breeding of T or of fissionable fuels, or for the burnup of radioac¬ tive nudear wastes. Thus, any DD-driven plant can dso be designed to produce neutron-generated products as wdl. For example, a plant producing electridty might dso use its output neutrons for the transmutation/ burnup of fission product wastes from conventiond nuclear reactors. It is estimated that DD systems which burn aU of the T they produce wiU be capable of breeding 2-3 times as much transmuted product as is potentiaUy possible in con- ventiond fusion reactor plant concepts, and up to 20-50 times as much as from fission breeder reactors (e.g. , Phemx-II or LMFBR). Also as noted before, nuclear fusion reacting systems of the 5 ; type herein wiU not generaUy con ine the charged partide pro¬ ducts- of the reaction. These aU appear with suffident energy to escape the exterπaUy-driven ion-confimn dectrostatic potentid weU, and wiU not be confined by the magnetic fidds used to support the dectrons reqdred for mdntenance of this dectrostatic wdl. They may be coUected on the walls or on any other structure of the system outside the confined ion-plaasma region. Since they are charged partides this method of operation offers the prospect of the direct, conversion of their energy to dectridty, by .the imposition of a high positive potentid on these surrounding walls/ structures. Thus it is another object of this invention to aUow the production of electricd energy by direct conversion of the energy of fusion product partides from their generation in devices of the type considered herdn. In DD systems the He3 and T produced can be coUected and recycled back into the system for further fusion reaction and additiond energy rdease with the D ions therein. Alternatively, the He3 and T products escaping the system codd be coUected and used as fusion fuel in DT or DHe3 fusion systems located elsewhere. Given a fusion system capable of burmng DD, there appears little incentive to use DT fuels for dvil/commercid applications. Conversdy, burmng high-neutron-output DT offers certdn new and unique capabilities in mUitary systems not previously attdnable by any other means, and such systems seem espeddly usefd for mUi¬ tary applications. Fusion by use of DT fuels can be accomplished in the system of the invention described herdn with smdler centrd dectric potentials than are needed for DD (or for any other fusionable fuels) . Such DT fusion systems have the property that 80% of their output energy appears as 14.1 Mev neutrons. This highly radioactive neutron output makes them of potentid use for various nationd defense missions, e.g. as smaU mobile ground-based radiation weapons, for remote irradiation • of mUitary targets with ther- mdnudear neutrons. Their smdl size, low power consumption, and mobUity dso make such systems uniquely sdted to a variety of mUitary uses in the space environment. These indude systems for remote inspace irradiation and radiation-counting inspection, radiation damage or kiU of opposing spacecraft and eqdpment, etc. Cdcdations of neutron spectrd output from such systems show that their spectrd energy distribution is simUar to that from rdatively "dean" "hot" ther¬ monuclear bombs, thus they codd also be usefd for some aspects of TN weapons output simdation. The large output and low cost of the energetic neutrons which constitute the output of DT burmng systems make these ideally economicdly sdted for use as neutron sources for the breeding/production of a variety of nudear fuels and other isotopes. These indude reactor grade nudear fuels (e.g. , approximatdy 3.5% enriched in U233 or Pu239 , etc. ), weapons-grade fissionable materid, low-cost T , and a variety of spedd trans-uramc isotopes which have unique uses in nudear weapons systems. Findly, if negative potentid wdl depths of 400-800 kev can be produced and mdntdned stably, as the current invention indicates, it is possible to burn non-radiative or radiation- free fusion fuels such as pBll or pLi6, which yidd ody He4 and He3 as their fusion products. Although such specid isotope fuels are more costly than DD done, the radiation- free character of the systems in which they operate makes these of unique vdue and application for various mUitary and space missions. Among these are moddated sdf- powered microwave power generators with power output much larger than moddated input power; space propdsion engine systems for rocket propdsion at very high performance levels, exceeding conven- tiond means by factors of 10-100; smdl, non-hazardous and light- weight space dectric power systems; mobUe mUitary power plants; surface ship and submarine propdsion systems which do not require any significant shidding; and even radiation- free unshidded pro¬ pdsion systems for drcraft. In any of these systems, the fusion products may be dlowed to escape the confined plasma region and their energy may be converted directly to electridty, if desired. In generd, the large gdn (G ) of these systems, even at smaU sizes (see Table 1) , makes their application to systems of modest size and: scde qdte strdghtforward. In fact, the smallest radiation-free systems codd be used for a variety of civU applica¬ tions on a locd " level; e.g. , power units for apartment complexes, smaU housing developments, single manufacturing plants of modest size, etc. Other dvU/commerdd applications are obvious for radiation-free systems; inducting ship propdsion, prime power for raUroad engines, and sdected steam-generating and/ or dectric power production plants, where spedd isotope fuel costs are not significant compared to locd costs of hazard prevention for radioactive fuds (espeddly DT) . In condusion it is worth noting that the basic device, as conceived, is not necessarily an "igmtion" device in which a certdn set of conditions must be achieved in order that the fusion reactions wiU become sdf-sustdmng. Rather it is inherently a power amplifier, in which (smdl) electric power is provided to the magne¬ tic fidd coils and electron and ion injectors of the system, and (large) fusion reaction powers are induced and caused to continue steadUy and stably within the machine' s confined plasma volume. This feature is a naturd resdt of the facts that: (a) electrons have gyro radii much smdler than the device radii; (b) fusion fuel ions have gyro radii comparable to the device radii, and; (c) fusion pro- ducts have gyro radii much larger than the device radii. AU of this ensures that: (a) electrons wUl be weU-trapped by the magnetic fields of the device; (b) plasma ions wUl not be trapped by these fidds but, rather, by the electrostatic fidds set up by the trapped electrons, and; (c) fusion product ions (e.g. , He4, He3, T , etc. ) , with mdti-Mev energies, will simply escape from the system entirely, carrying their energy with them. Because of this latter feature, the device may exhibit an "ignition-like" property, in which the imtiation of significant fusion reactions can resdt in the ejection of large numbers of positive charges which, in turn, increase the fusion reaction rate by deepemng the dectrostatic wdl confimng the fusion reactive plasma. The richness and diversity of fuels and processes for fusion power production offered by this new and novel means of con¬ finement and of adding energy to plasmas and charged partides offers many new possibUities for umque applications to conventiond and non-conventibnd energy plants. In addition, entirdy new types of energy/power systems for dvU/commerdd, space, and mUitary uses are made possible by this device. It wUl be apparent that the broad teachings of the present invention can be profitably applied to spedfic embodiments and applications far beyond what is set forth above for the purposes of illustration. The present invention shodd therefore not be in any way deemed limited to such spedfic embodiments and applications, but shodd instead be deemed fdly commensurate in scope with the following eldms.

Claims: WHAT B CLAIMED IS : 1. A method of controlUng positively charged particles comprising the steps of: (a) generating a quasi-sphericd magnetic fidd; (b) using sdd generated magnetic field to confine electrons and so to generate a negative potentid weU; and (c) using sdd negative potentid wdl to confine sdd positively charged partides. 2. A method as ddmed in Cldm 1 wherein sdd step (a) further comprises generating a magnetic fidd aU the cusps of which are point cusps and having edge contours corresponding to the edges of a truncated regdar polyhedron, with the signs of the cusps dternating from face-to-face of the truncated regdar polyhedron. 3. A method as ddmed in Cldm 1 wherein sdd step (a) further comprises generating a surface cusp magnetic fidd having edge contours corresponding to a superposition of at least two trun¬ cated polyhedra. 4. A method as ddmed in Cldm 1 wherein sdd step (a) further comprises generating a surface cusp magnetic fidd having edge contours corresponding, to a superposition of at least two poly¬ hedra. 5. A method as ddmed in Cldm 1 wherein sdd step (a) further comprises generating a surface cusp magnetic fidd having edge contours corresponding to a superposition of at least a poly- hedron and a truncated polyhedron. 6. A method as ddmed in Cldm 1 wherein sdd step (a) further comprises generating the quasi-sphericd magnetic fidd to be constant with time. 7. A method as ddmed in Cldm 1 wherein sdd step (a) further comprises generating the quasi-sphericd magnetic fidd to vary with time. 8. A method as ddmed in Cldm 1 wherein sdd step (b) further comprises injecting sdd electrons into the center of sdd generated magnetic fidd. 9. A method as ddmed in Cldm 1 wherein sdd step 5 (c) further comprises injecting sdd charged partides into sdd generated negative potentid wdl. 10. A method as ddmed in Cldm 1 wherdn sdd charged partides comprise ions of at least one of the isotopes of hydrogen. 11. A method as ddmed in Cldm 1 wherein sdd charged ° partides comprise ions of one of the isotopes of an dement taken from the group consisting of Uthium, beryllium, helium, and boron. 12. A method as ddmed in Cldm 1 wherdn sdd step (b) further comprises the step of varying the depth of sdd generated negative potentid wdl periodicaUy with time. 5 13. A method as ddmed in Cldm 12 wherein the weU depth is varied by injecting electrons into the center of sdd generated magnetic fidd at a periodicdly moddated injection voltage. 14. A method as ddmed in Cldm 12 wherein the wdl 0 depth is varied by injecting electrons into the center of sdd generated magnetic fidd at a periodicdly moddated injection current. 15. An apparatus for controlling charged partides compri¬ sing: 5 means for generating a quasi-sphericd magnetic fidd; means for injecting dectrons into the center of sdd magnetic fidd and so for forming a negative potentid wdl within sdd magnetic fidd; and means for injecting charged partides into sdd nega- 0 tive potentid wdl. 16. An apparatus as ddmed in Cldm 15 wherein sdd injecting means continuously injects the charged partides into the negative potentid wdl. 17. An apparatus as ddmed in Cldm 15 wherdn sdd injecting means injects pdses of charged partides into the negative potentid wdl. 18. An apparatus as ddmed in Cldm 15 wherdn sdd magnetic: fidd generating means is for generating a magnetic fidd aU the. cusps of which are point cusps. 19. An apparatus as ddmed in Cldm 15 wherdn sdd magnetic fidd generating means is further operable to generate a magnetic field having edges corresponding to those of a truncated polyhedron. 20. An apparatus as ddmed' in Cldm 19 wherdn sdd magnetic fidd generating means is operable to generate point cusps at positions corresponding to the centers of faces of sdd truncated regdar polyhedron. 21. An apparatus as ddmed in Cldm 20 wherein sdd electron injecting means is arranged to inject sdd dectrons through one of sdd point cusps dong a first line corresponding to an axis of sdd truncated polyhedron. 22. An apparatus as ddmed in Cldm 21 further comprising a second dectron injection means arranged opposed to sdd first mentioned electron injection means across sdd magnetic field generating means. 23. An apparatus as ddmed in Cldm 15 wherdn sdd means for injecting charged partides is operable to inject positive ions of one of deuterum, and tritium. 24. An apparatus as ddmed in Cldm 20 wherein sdd electron injecting means is arranged to inject sdd electrons through one of sdd point cusps dong a first line intersecting an axis of sdd truncated polyhedron at an angle. 25. An apparatus as ddmed in Cldm 20 wherein sdd electron injecting means is arranged to inject sdd dectrons dong a first anndus through one of sdd point cusps, the centrd axis of sdd first anndus corresponding to an axis of sdd truncated regdar poly¬ hedron. 26. An apparatus as ddmed in Cldm 25 wherdn sdd means for injecting electrons is operable to generate a beam with rotation. 27. An apparatus as ddmed in Cldm 20 wherein sdd charged partide injecting means is arranged to inject sdd charged partides through one of sdd point cusps. 28. An apparatus as ddmed in Cldm 27 further comprising a second charged partide injection means arranged opposed to sdd first mentioned charged partide injection means across sdd magnetic fidd generating means. 29. An apparatus as ddmed in Cldm 20 wherdn sdd charged partide injecting means injects sdd partides in a beam dong a line corresponding to an axis of sdd truncated polyhedron. 30. An apparatus as ddmed in Cldm 29 wherein sdd beam is injected with rotation. 31. An apparatus as ddmed in Cldm 20 wherein sdd charged partide injecting means is arranged to inject sdd charged partides dong a second anndus through one of sdd point cusps, the centrd axis of sdd second anndus corresponding to an axis of sdd truncated regdar polyhedron. 32. An apparatus as ddmed in Cldm 31 wherein sdd charged partides form an anndar beam having rotation. 33. An apparatus as cldmed in Cldm 19 wherein sdd magnetic field generating means comprises a plurdity of current carrying members respectively disposed at positions corresponding to the edges of sdd truncated regdar polyhedron. 34. An apparatus as in Cldm 33 wherein sdd current- carrying members are driven by dternating current supplies to pro¬ duce oscillating magnetic fields. 351, An apparatus as ddmed in Cldm 33 wherein sdd polyhedrorr iss one taken from the group consisting of a tetrahedron, a hexahedron, a. truncated cube, and a dodecahedron. 36. An apparatus as ddmed in Cldm 15 wherein sdd magnetic field generating means is further operable to generate a magnetic field conforming substantiaUy in shape to a superposition of at least two polyhedra. 37. An apparatus as ddmed in Cldm 36 wherein sdd magnetic field generating means comprises a plurality of current carrying members respectively disposed at positions corresponding to the edges of sdd superposition. 38. An apparatus as in Cldm 37 wherein sdd current- carrying members are driven by dternating current supplies to pro¬ duce oscUlating magnetic fields. 39. An apparatus as ddmed in Cldm 15 wherein sdd magnetic field generating means is further operable to generate a magnetic field substantidly conforming in shape to a superposition of at least two truncated polyhedra. 40. An apparatus as ddmed in Cldm 39 wherein sdd magnetic field generating means comprises a plurdity of current carrying members respectively disposed at positions corresponding to the edges of sdd superposition. 41. An apparatus as in Cldm 40 wherein sdd current- carrying members are driven by dternating current supplies to pro- duce oscillating magnetic fields. 42. An apparatus as ddmed in Cldm 15 wherein sdd magnetic field generating means is further operable to generate a magnetic field substantiaUy conforming in shape to a superposition of a polyhedron and a truncated polyhedron. 43. An apparatus as ddmed in Cldm 42 wherein sdd magnetic field generating means comprises a plurdity of current carrying members respectively disposed at positions corresponding to the edges of sdd superposition. 44. An apparatus as in Cldm 43 wherein sdd current- carrying members are driven by dternating current supplies to pro¬ duce oscillating magnetic fields. 45. A method of confining positive ions and causing sdd positive ions to undergo mutual nuclear coUisiond reactions comprising the steps of: (a) generating a quasi-sphericd magnetic fidd; (b) confimng electrons in sdd quasi-sphericd magne¬ tic field thereby generating a negative potentid wdl; and (c) confining sdd positive ions in sdd negative potentid weU at suffident density and with sufficient energy to cause sdd coUisiond reactions. 46. A method as of Cldm 45 wherein the density of positive ions is increased by continuous injection of sdd positive ions so that circdating currents across the confined region become larger than those due to a single pass injection done. 47. A method as of Cldm 46 wherein the circdation of positive ions is accompamed by a convergence of positive ion current flow, with sphericaUy geometric convergence, resdting in large den¬ sities of positive ions at the center of the confimng potentid wdl.

Inventors: BUSSARD ROBERT W, BUSSARD, ROBERT, W.
Applicants: ENERGY MATTER CONVERSION CORP, ENERGY/MATTER CONVERSION CORPORATION, INC.
Application year: 1986
Main classification: G21B1
IPC codes: H05H1