The subject of this work is computational modeling of neutron transport relevant to economical and safe operation of nuclear facilities. The general mathematical model of neutron transport is provided by the linear Boltzmann’s transport equation and the thesis begins with its precise mathematical formulation and presentation of known conditions for its well-posedness. In the following part, we ...

We discuss iterative methods for computing criticality in nuclear reactors. In general this requires the solution of a generalised eigenvalue problem for an unsymmetric integro-differential operator in 6 independent variables, modelling transport, scattering and fission, where the dependent variable is the neutron angular flux. In engineering practice this problem is often solved iteratively, u...

We consider transport properties of the hypernuclear matter in neutron star cores. In particular, we calculate thermal conductivity, shear viscosity, and momentum transfer rates for np$\Sigma^{-}\Lambda e\mu$ composition dense $\beta$--equilibrium baryon number densities range $0.1-1$~fm$^{-3}$. The calculations are based on interactions treated within framework non-relativistic Brueckner-Hartr...