A tokamak fusion reactor. The tokamak fusion reactor comprises a toroidal plasma chamber and a plasma confinement system arranged to generate a magnetic field for confining a plasma in the plasma chamber. The plasma confinement system comprises toroidal field magnets, which generate a magnetic field, B.sub.T0, in the centre of the plasma. The toroidal field magnets are configured such that, in use, the magnetic field, on conductor of the toroidal field magnets is at least 20 Tesla. The plasma confinement system is configured such that, in use, the plasma has: an aspect ratio, A, of 2 or less; an elongation, K, of at least 2; a major radius R.sub.0 of 3.5 meters or less; a normalised beta of at least 3; an engineering safety factor, q.sub.eng, of at least 2.0; wherein the engineering safety factor q.sub.eng is defined as: g.sub.eng=5 B.sub.T0R.sub.0K/A.sup.2I.sub.P where I.sub.p is the plasma current; a ratio of the fusion gain, Q.sub.fus to the fusion power, P.sub.fus, greater than 0.03 MW.sup.−1 at fusion power, P.sub.fus, less than 500 MW.

Described are toroidal devices to produce steady state, helical, Taylor-Couette-like magnetohydrodynamic singular structure flows in plasma or other conductive fluids with full magnetohydrodynamic helicity. Linking of two or more such toroidal devices can be used to generate a laminar kinematic dynamo. Only one is required to confine plasma at the pressures and for times required to produce nuclear fusion. Such high-temperature plasma can also be used for centrifugal ionic separation, nuclear transmutations at production quantity, and in the near term as a study tool in the development of materials to withstand high temperature and neutron flux. Plasma is a high-energy state of matter capable of relativistic velocity en masse, and as such, relativistic plasma or other conductive fluid devices are a means to generate gravity.

Systems, apparatuses, and methods are provided for dual-pass amplification of laser beams along a common beam path. An example method can include generating a first laser beam and a second laser beam. Subsequently, the example method can include performing dual-pass amplification of the first laser beam and the second laser beam along a common beam path. In some aspects, the first laser beam can include a first wavelength, the second laser beam can include a second wavelength different from the first wavelength.

Systems, devices, and methods for generating an orbital confinement fusion reaction are described. An orbital confinement fusion device can include a cathodic inner electrode defining a longitudinal axis of the device. The inner electrode can include an emitter material. The orbital confinement fusion device can include an anodic outer electrode, concentric with the longitudinal axis and defining a chamber between the inner electrode and the outer electrode. The orbital confinement fusion device can also include a plurality of magnetic field generators disposed in a coaxial arrangement relative to the longitudinal axis. The plurality of magnetic field generators can be configured to form a magnetic field parallel to the longitudinal axis in the chamber.

A superconducting magnet for producing part of a substantially toroidal field in a device is described. The magnet comprises: a set of conductors comprising one or more first conductors (31f) and one or more second conductors (32f), and a set of joints (33). Each of the joints (33) connects a region of a first conductor (31f) with a region of a second conductor (32f) to form a series of alternating first and second conductors corresponding to at least part of a winding of the magnet. Each of the joints (33) is positioned away from a midplane of the toroidal field. The joints (33) are positioned on alternating sides of the midplane. Each first conductor (3 If) passes through the midplane at a smaller distance from an axis of rotation of the toroidal field than does each second conductor (32f). Each of the regions is elongate and extends in a direction at least partly away from the midplane.

The present disclosure provides a stellarator magnet based on cubic permanent magnet blocks and an arrangement optimization method thereof. For the characteristic that a three-dimensional magnet coil of a stellarator is complex in structure, the present disclosure provides the stellarator magnet based on the cubic permanent magnet blocks with uniform magnetization, same magnetization and same size; the magnetization directions of the cubic permanent magnet blocks are defined in a limited number of fixed alternative directions; the magnetic field configuration of the stellarator is generated by dipole magnetic fields provided by the permanent magnet blocks and planar coils, so that the device complexity of the stellarator is reduced, and the difficulty and cost of the machining and installation of the magnet are reduced. The shape of the permanent magnet blocks can be replaced by other regular shapes, and the permanent magnet is still formed by the permanent magnet blocks with same shape, same size, uniform magnetization and same magnetization. For the magnet, the present disclosure provides a magnet arrangement optimization method of ‘local compensation’ and related optimization strategies of ‘threshold truncation,’ ‘global fine tuning,’ etc., for meeting different optimization requirements on accuracy of the magnetic fields, usage qualities of magnets, etc., and a magnetic field meeting designing requirements can be obtained.

A method of controlling a plasma in a nuclear fusion reactor. The nuclear fusion reactor comprises sensors and plasma control inputs. An initial control model is provided, relating readings of at least a subset of the sensors to control of the plasma control inputs. A control loop is performed, comprising: operating the plasma control inputs in dependence upon the sensors according to the control model; determining correlations between readings of each of the sensors, and/or between readings of the sensors and states of the plasma control inputs; and adjusting the control model based on the determined correlations.

Provided herein are systems, devices, articles of manufacture, and methods for generating neutrons employing a high energy ion beam target (HEM target) and a target backing configured to be in contact with the bottom surface of the HEIB target (e.g., to generate an ion beam target assembly). In certain embodiments, the HEM target has a thickness that is less than the penetration depth of protons or deuterons in the high energy ion beam that strikes the target. In certain embodiments, the target backing comprises a high hydrogen diffusion metal (e.g., palladium), has open spaces dispersed throughout for reduced proton diffusion distances, and has a shape and thickness such that all, or virtually all, of the protons or deuterons that pass through the HEIB target are stopped. Also provided herein are systems, devices, and methods for changing targets in an ion beam accelerator system.

Methods, apparatuses, devices, and systems for producing and controlling and fusion activities of nuclei. Hydrogen atoms or other neutral species (neutrals) are induced to rotational motion in a confinement region as a result of ion-neutral coupling, in which ions are driven by electric fields. The controlled fusion activities cover a spectrum of reactions including aneutronic reactions such as proton-boron-11 fusion reactions.

Described are concepts directed toward systems, structures and techniques to create low-resistance, high current capacity, demountable solder joint connections. Such systems, structures and techniques may be used to simultaneously create low-resistance, high current capacity, demountable solder joint connections at multiple locations between no insulation (NI) superconductors and in particular between NI high temperature superconductors (HTS) such as may be used in NI-HTS magnets.