Nuclear reactors: Types of reactors, thermal and fast reactors, reactor components, Power plant system, future reactors, nuclear fuel utilization.Neutron diffusion theory: The neutron flux and reaction rates, the diffusion coefficient, derivation of the neutron diffusion equation, boundary conditions, external neutron sources, neutron diffusion in non-multiplying homogenous media, multi-region, slab, spherical, and cylindrical geometries.
Neutron diffusion in multiplying homogenous media (the reactor core), time dependent core, concept of criticality, criticality condition, reflected core, reflector savings, slab, spherical, and cylindrical geometries, flux and power distributions.Energy and space dependent reactor, multi-group theory and cross sections, two group theory, modified one group.Numerical solution of the neutron diffusion equation: one dimensional discretization, solution algorithm and flow chart, Two dimensional discretization, two group 1D and 2D.Diffusion codes (no burn-up): 1D and 2DB codes, scope of the overall calculation task, preparation of the input file, interpretation of the output file, sample problems excluding.
