Application of axial seed magnetic fields in the range 20-100 T that compress to greater than 10,000 T (100 MG) under typical NIF implosion conditions may significantly relax the conditions required for ignition and propagating burn in NIF ignition targets that are degraded by hydrodynamic instabilities. Such magnetic fields can: (a) permit the recovery of ignition, or at least significant alpha particle heating, in submarginal NIF targets that would otherwise fail because of adverse hydrodynamic instability growth, (b) permit the attainment of ignition in conventional cryogenic layered solid-DT targets redesigned to operate under reduced drive conditions, (c) permit the attainment of volumetric ignition in simpler, room-temperature single-shell DT gas capsules, and (d) ameliorate adverse hohlraum plasma conditions during laser drive and capsule compression. In general, an applied magnetic field should always improve the ignition condition for any NIF ignition target design.

An illumination source includes a laser driver unit configured to emit a plasma sustaining beam. An ingress collimator receives the plasma sustaining beam and produces a collimated ingress beam. A focusing optic receives the collimated ingress beam and produce a focused sustaining beam. A sealed lamp chamber contains an ionizable media that, once ignited, forms a high intensity light emitting plasma having a waist size smaller than 150 microns. The sealed lamp chamber further includes an ingress window configured to receive the focused sustaining beam and an egress window configured to emit the high intensity light. An ignition source is configured to ignite the ionizable media, and an exit fiber is configured to receive and convey the high intensity light. The high intensity light is white light with a black body spectrum, and the exit fiber has a diameter in the range of 200-500 micrometers.

An illumination source includes a laser driver unit configured to emit a plasma sustaining beam. An ingress collimator receives the plasma sustaining beam and produces a collimated ingress beam. A focusing optic receives the collimated ingress beam and produce a focused sustaining beam. A sealed lamp chamber contains an ionizable media that, once ignited, forms a high intensity light emitting plasma having a waist size smaller than 150 microns. The sealed lamp chamber further includes an ingress window configured to receive the focused sustaining beam and an egress window configured to emit the high intensity light. An ignition source is configured to ignite the ionizable media, and an exit fiber is configured to receive and convey the high intensity light. The high intensity light is white light with a black body spectrum, and the exit fiber has a diameter in the range of 200-500 micrometers.

An inductively coupled plasma (ICP) torch is described that includes a tapered outer end. A system embodiment includes, but is not limited to, a tubular sample injector configured to receive an aerosolized sample in an interior defined by walls of the tubular sample injector; an inner tube surrounding at least a portion of the tubular sample injector to form a first annular space between the inner tube and the walls of the tubular sample injector, the inner tube defining at least one inlet port for introduction of an auxiliary gas into the first annular space; and an outer tube surrounding at least a portion of the inner tube to form a second annular space, the outer tube defining at least one inlet port for introduction of a cooling gas into the second annular space, the outer tube having a flared region at an outlet of the outer tube.

An inductively coupled plasma (ICP) torch is described that includes a tapered outer end. A system embodiment includes, but is not limited to, a tubular sample injector configured to receive an aerosolized sample in an interior defined by walls of the tubular sample injector; an inner tube surrounding at least a portion of the tubular sample injector to form a first annular space between the inner tube and the walls of the tubular sample injector, the inner tube defining at least one inlet port for introduction of an auxiliary gas into the first annular space; and an outer tube surrounding at least a portion of the inner tube to form a second annular space, the outer tube defining at least one inlet port for introduction of a cooling gas into the second annular space, the outer tube having a flared region at an outlet of the outer tube.

An object of the present invention is to efficiently improve uniformity of energy lines to be irradiated. A method of determining nuclear fusion irradiation coordinates according to the present invention is a method of calculating irradiation coordinates when energy lines are irradiated onto a nuclear fusion target, and comprises an initial arrangement step S202 of virtually arranging electric charges Q.sub.i at initial coordinates of the number of irradiation coordinates N.sub.B on a spherical surface S.sub.0 set by using random numbers, a coordinate analysis step S203 of analyzing coordinates r.sub.i of the electric charges Q.sub.i in time series based on coulomb forces acting among the electric charges Q.sub.i by constraining the coordinates r.sub.i onto the spherical surface S.sub.0, potential evaluation steps S205 and S206 of determining a timing at which potential energies of the electric charges Q.sub.i were stabilized based on the coordinates r.sub.i, and an irradiation coordinate deriving step S207 of deriving coordinates r.sub.i at the timing at which potential energies were stabilized as irradiation coordinates of energy lines in a case where a nuclear fusion target is arranged at the center of the spherical surface S.sub.0.

An object of the present invention is to efficiently improve uniformity of energy lines to be irradiated. A method of determining nuclear fusion irradiation coordinates according to the present invention is a method of calculating irradiation coordinates when energy lines are irradiated onto a nuclear fusion target, and comprises an initial arrangement step S202 of virtually arranging electric charges Q.sub.i at initial coordinates of the number of irradiation coordinates N.sub.B on a spherical surface S.sub.0 set by using random numbers, a coordinate analysis step S203 of analyzing coordinates r.sub.i of the electric charges Q.sub.i in time series based on coulomb forces acting among the electric charges Q.sub.i by constraining the coordinates r.sub.i onto the spherical surface S.sub.0, potential evaluation steps S205 and S206 of determining a timing at which potential energies of the electric charges Q.sub.i were stabilized based on the coordinates r.sub.i, and an irradiation coordinate deriving step S207 of deriving coordinates r.sub.i at the timing at which potential energies were stabilized as irradiation coordinates of energy lines in a case where a nuclear fusion target is arranged at the center of the spherical surface S.sub.0.

A method and apparatus for generating a pulsed jet of fluid, and transforming the jet into a plasma. The method includes using a high-pressure rapid solenoid valve, and a pipe mounted on an outlet opening of the solenoid valve to produce a pulsed fluid jet which is sub-millimetric in size, and the atomic density of which is more than 10.sup.20 cm.sup.3.

A system and apparatus for controlled fusion in a field reversed configuration (FRC) magnetic topology and conversion of fusion product energies directly to electric power. Preferably, plasma ions are magnetically confined in the FRC while plasma electrons are electrostatically confined in a deep energy well, created by tuning an externally applied magnetic field. In this configuration, ions and electrons may have adequate density and temperature so that upon collisions they are fused together by the nuclear force, thus forming fusion products that emerge in the form of an annular beam. Energy is removed from the fusion product ions as they spiral past electrodes of an inverse cyclotron converter. Advantageously, the fusion fuel plasmas that can be used with the present confinement and energy conversion system include advanced (aneutronic) fuels.

A single-pass heavy-ion fusion system for power production from fusion reactions alone, power production that uses additional energy of fission reactions obtained by driving a sub-critical fission pile with the neutrons from fusion reactions, destroying high-level and/or long-lived radioactive waste by intense bombardment with fusion neutrons, or for the production of neutron beams for various applications includes a new arrangement of current multiplying processes that employs a multiplicity of isotopes to achieve the desired effect of distributing the task of amplifying the current among all the various processes, to relieve stress on any one process, and to increase the design margin for assured ICF (inertial confinement fusion) ignition for applications including but not restricted to the above list. The energy content and power of the ignition-driver pulses are greatly increased, thus increasing intensity of target heating and rendering reliable ignition readily attainable.