Simulation of multigroup X-ray, alpha-particle and neutron transport in ion beam driven ICF target.

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Abstract
A one-dimensional Lagrangian code, MEDUSA-IB for the analysis of ion beam fusion target behavior was developed. The code included multigroup X-ray, α-particle and neutron transport models. Photon transport equation was solved by variable Eddington method. Particle tracking method and collision probability method were used for the simulation of α-particle and neutron transport respectively. Temperature dependent ion beam energy deposition was also considered. Each routine of the code was verified separately. The analysis of a bare 1 mg DT target after ignition showed that only neutron transport slightly decreases fusion yield. The analysis of a reactor-size hollow single shell target containing 4.2 mg DT fuel, UTLIF target showed: Radiation and α-particle transport, temperature dependence of ion beam stopping and the equation of states decreased fusion gain when they were considered accurately. Neutron transport slightly increased the gain. The momentum deposition of ion beam and α-particles had very slight effects.

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