Experimental model studies for a fusion reactor blanket

In this thesis an investigation is presented for checking the available cross section data for blanket materials by comparing results from measurements and numerical calculations on various nuclear properties of a blanket model. The blanket consists of a stainless steel cylinder filled with pure lithium metal. A neutron generator based on the D-T reaction is used for a simulation of the fusion neutron source. For an enhancement of the tritium production, this model can be surrounded with a graphite layer; an inner beryllium layer can also be introduced. The gas counting and the liquid scintillation technique prove to be suitable techniques to measure the space dependent tritium production in the blanket model. From the measured saturation activities neutron spectra are derived with the use of an unfolding method. Several methods are compared. Neutron spectra are calculated with a numerical program based on a Monte Carlo method