One-dimensional modelling of neutron leakage from spherical shell assemblies with openings

Abstract A modelling of the neutron leakage from source driven systems with openings e.g. from fusion reactor blankets using a one-dimensional tranport code is presented. The concept is based upon a numerical transfer of neutron losses physically occurring outside of the system into its centre. This is achieved with a fictitious neutron absorber representing the apertures in the real system, which is /computationally/ occupying the central zone. A very good accordance with respective three-dimensional calculations has been obtained for wide range (from the neutronic point of view) of the blanket configurations.