babak khanbabaei

Indirect drive inertial confinement fusion (ICF) holds promise for achieving practical energy generation through controlled fusion reactions. However, the efficiency of ICF is constrained by the Be ablator material used to contain the fuel. To overcome this limitation, researchers have proposed doping Be with various elements. In this study, we investigate the effects of Na and Br dopants, incorporated at concentrations of 4.86% and 2.1%, respectively, using a one-dimensional MULTI-IFE hydrodynamic code. This code serves as a numerical tool dedicated to analyzing Inertial Fusion Energy microcapsules, facilitating the examination of the Be ablator's performance in indirect drive ICF. Our results indicate that the addition of a beryllium layer doped with Na and Br significantly enhances the target gain, elevating it from the break-even value (G ≈ 1) to approximately G ≈ 12. Furthermore, we delve into the impact of these dopants on the plasma fuel conditions during the implosion, shedding light on the underlying physics of the system. These findings demonstrate that Na and Br doping in the Be ablator represents a viable approach for improving the efficiency of indirect drive ICF, potentially paving the way for the development of practical fusion energy systems.

A numerical model was developed and a system of the nonlinear equations of deuterium-tritium burn-up in inertial confinement fusion have been solved to find the minimum conditions which are required for the formation of hot spot and starting the thermonuclear reactions in a self-sustaining mode. The effect of all the dominant phenomena in the nonequilibrium plasma, including the alpha particle energy deposition in the hot spot and transferring to ions and electrons, ions-electron coupling energy, and the main photons-matter interactions, which includes the bremsstrahlung radiation and the Compton scattering, were investigated. By using the Klein-Nishina equation for scattering cross-section of high energy photons, the effects of the photon-matter interactions from a relativistic point of view have also been studied. It was shown that the change of photon distribution shape can have a significant effect on the photon temperature, the photon-electron coupling energy and as a result on the electrons and the ions’ temperature in a diluted plasma.

Shock ignition (SI) is one of the methods considered in the concept of inertial confinement fusion (ICF). This two-step ICF process separates fuel assembly and ignition, relaxing the driver requirements and promising high gains. In SI scheme, a strong spherical shock wave converging at the end of the initial laser pulse ignites the pre-compressed fuel. In shock ignition, when the hot spot pressure is much higher than the surrounding cold fuel pressure, the fuel structure is considered non-isobaric. In this research, ignition conditions and fuel efficiency in shock ignition method were investigated. Then, the fuel efficiency correlations of total fuel energy, fuel gain and hot-spot radius in a non-isobaric model of fuel assembly were improved and compared with the numerical results of deuterium-tritium (DT) homogeneous fuel in SI scenario. Calculations showed that the hot spot formation conditions depend on the hot spot density and the surrounding cold fuel. Furthermore, using the improved energy efficiency equation, the role of physical parameters such as fuel mass and different ratios of hot spot pressure to the surrounding cold fuel pressure in energy efficiency were investigated.

Shock ignition (SI) is one of the attractive topics for inertial confinement fusion (ICF). This two-step ICF process separates fuel assembly and ignition, relaxing the driver requirements and promising high gains. One of the main concerns about current working on nuclear power Reactor is the potential hazards of their radioactive waste. In the design of future fusion power plants, there still exist radiological hazards due to accumulation of byproduct tritium in blanket layer and also collisions between 14.1MeV neutrons released from Deuterium- Tritium(DT) fusion reaction and nearly all fusion reactor building materials. Therefore, in this paper, ignition requirements and fuel gain of non-equimolar DT fuel pellet have been studied in SI scheme. Our calculations show that the hot-spots formation conditions depend on densities of hot-spot and its surrounding cold fuel. Finally, the role of physical parameters on energy gain is investigated, including fuel mass, the ratio of hot- spot pressure to cold fuel pressure, different tritium weight fractions and isentrope parameter.