Diagnostics of some parameters of a fusion reactor blanket model

The results of the tritium production measurements in a cylindrical model of a lithium blanket of fusion reactor are presented. A successful trial of the use of LiF thermoluminescence detectors (TLD) together with liquid scintillation method (LS) for blanket diagnostics (fast neutron flux density, energy deposition and tritium production) is presented. The neutron spectra in the blanket model in the proximity of a neutron source are determined experimentally using activation method and SAND-2 unfolding code with 3 available nuclear cross sections data sets (ENDF/B-4, ENDF/B-5, ENDL). The results are compared with those obtained with Monte Carlo (MORSE) and EPR library calculated spectra. 5 refs.,8 figs., 8 tabs. (author)