An AC magnetic sensor is presented for measuring the high speed and high strength magnetic field generated in Z-pinch fusion machines. The proposed magnetic sensor provides the measurement of magnetic fields across a broadband frequency range. The simulation of magnetic probe is presented using a SPICE simulation software LTspice. The magnetic sensors are installed in a Pulsotron-3 Z-pinch machine and measured performance of the sensor are presented. This sensor also can be used to check the ignition conditions of the Z-Pinch by measuring the magnetic field generated by the output streams of large number of reacted alpha particles. The equations for measuring non-stationary magnetic field due to rapidly varying electric currents and a LTspice simulation file are provided to help the engineers to design, build, and install this kind of sensors.

The measured results of two tests T3073 and T3074 performed in 28 August, 2020 are presented in this paper. Tests are conducted in the z-pinch type nuclear fusion reactor Pulsotron-3 with the target loaded with Hydrogen-Boron (H+B11) thermonuclear fuel. A group of Energy Recovery Coils (ERCs) were mounted to recover the electric energy directly from the plasma for the first time in the world and ERCs stored the energy in several large capacitors. During the test T3073 and T3074 the energy recovery capacitors recovered 22.59% and 17.74% of the injected energy at the target. A magnetic sensor MAG-4 consisting of inductor coils and dipoles were installed in Pulsotron-3 to measure the Time Of Flight (TOF) of the plasma and the magnetic field generated due to nuclear fusion. Magnetic fields more than 4 megateslas are obtained during the two tests. It is also observed that Pulsotron-3 with the target loaded with thermonuclear fuel generated 20-34 times larger peak magnetic fields and 12-18 times larger stabilized magnetic fields compare to the tests done using unloaded target (dummy loads). In this proposed technology Pulsotron-3 utilizes thermonuclear fuel to generate clean electric power without CO2 footprint and reduce the operational cost. This industrial approach is a promising solution that can reduce world emissions to zero in less than 8 years.

Several tokamaks structures containing 500 keV protons to be used in P-B11 fusion were simulated. In order to find the optimal confinement configuration, the simulation was helped by an evolutionary algorithm running 145,000 simulations. The results are presented in this paper. According to the simulations the tokamak structure can be operated to reach ignition using the proposed plasma mode that includes the use of low electron temperature and high thermal energy protons in the plasma (500 keV).