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.

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.

The present disclosure is directed to systems for generating neutrons, the systems including a stellarator optimized for fast particle finement. In some embodiments, the stellarator optimized for fast particle confinement is selected from a quasi-axisymmetric stellarator, a quasi-symmetric stellarator, a quasi-isodynamic stellarator, or a quasi-omnigenous stellarator. The present disclosure is also directed to methods of generating neutrons using the systems of the present disclosure and, in particular, systems incorporating a stellarator optimized for fast particle confinement.

Disclosed herein is a stellarator comprising two sets of coils, namely a set of encircling coils which encircle the plasma axis, and a set of shaping coils which do not encircle any other coil or the plasma. In some embodiments, the encircling coils include a structural element to maintain their shape under magnetic forces. In some embodiments, the shaping coils are mounted onto one or more structural elements which, together with the shaping coils, constitute a field shaping unit. Also disclosed is a controller which may modify the electrical current flowing in one or more subsets of the coils in order to achieve target plasma parameters. Also disclosed is a method of designing a set of shaping coils by discretizing a surface dipole or current potential distribution.

This invention has evolved from the discovery of how to correctly blend Einstein's Special Relativity into nuclei and atoms. That blending greatly simplifies understanding of nuclear physics. Pairs of electrically neutral relativistically warped nuclei share a huge configuration electrostatic nuclear strong force with a 1/r to the 5.3 power short range. This strong force can be either repulsive or attractive. The attractive strong force causes pairs of neutralized anti matter protons and neutralized deuterons to attract, fuse, dewarp and produce an enormous amount of relativistic mass energy. The new constituents of plasma in Tokamak and Stellarator magnetic confinement machines will consist of protons, deuterons and, for the first time ever, electrons. There is no residue from this relativistic nuclear fusion reaction. The neutrinos produced pass quickly through the walls of the reaction vessel and leave earth.

Systems, methods and apparatus are provided through which in some implementations an experimental fusion system includes a housing having a hollow toroidal interior chamber, wherein the hollow toroidal interior chamber includes an interior surface having rifling.

Disclosed herein is a stellarator comprising two sets of coils, namely a set of encircling coils which encircle the plasma axis, and a set of shaping coils which do not encircle any other coil or the plasma. In some embodiments, the encircling coils include a structural element to maintain their shape under magnetic forces. In some embodiments, the shaping coils are mounted onto one or more structural elements which, together with the shaping coils, constitute a field shaping unit. Also disclosed is a controller which may modify the electrical current flowing in one or more subsets of the coils in order to achieve target plasma parameters. Also disclosed is a method of designing a set of shaping coils by discretizing a surface dipole or current potential distribution.

Disclosed herein is a stellarator comprising two sets of coils, namely a set of encircling coils which encircle the plasma axis, and a set of shaping coils which do not encircle any other coil or the plasma. In some embodiments, the encircling coils include a structural element to maintain their shape under magnetic forces. In some embodiments, the shaping coils are mounted onto one or more structural elements which, together with the shaping coils, constitute a field shaping unit. Also disclosed is a controller which may modify the electrical current flowing in one or more subsets of the coils in order to achieve target plasma parameters. Also disclosed is a method of designing a set of shaping coils by discretizing a surface dipole or current potential distribution.

Disclosed herein is a stellarator comprising two sets of coils, namely a set of encircling coils which encircle the plasma axis, and a set of shaping coils which do not encircle any other coil or the plasma. In some embodiments, the encircling coils include a structural element to maintain their shape under magnetic forces. In some embodiments, the shaping coils are mounted onto one or more structural elements which, together with the shaping coils, constitute a field shaping unit. Also disclosed is a controller which may modify the electrical current flowing in one or more subsets of the coils in order to achieve target plasma parameters. Also disclosed is a method of designing a set of shaping coils by discretizing a surface dipole or current potential distribution.

All magnetic nuclear fusion devices face common technical challenges related to power and particle control arising from the close proximity of a thermonuclear plasma to the plasma-facing component. The plasma-facing component is subjected to high incident power density and erosion processes, and must facilitate the efficient remove of the fusion-ash. In the past, limiters and divertors have been used in magnetic fusion devices for this purpose. These are discussed and extended to a new concept, the stochastic mantle, which utilizes a stochastic magnetic field layer to disperse power on the plasma-facing component to the maximum extent possible. Further, if operated at sufficient plasma collisionality, it reduces the energy of particles incident on the plasma-facing component, globally reducing erosion by physical sputtering, while producing high gas pressures for fusion-ash removal through pumping ducts. The approach is particular suited for stellarators, but others devices may be considered.