Blanket Experiments Using Enriched Li2Tior/Ferritic Steel/ Beryllium Assemblies and D-T Fusion Neutrons

At Fusion Neutronics Source (FNS), we have done experiments with thermal-type breeding blanket mock-rrps using lithium titanate as breeder material, beryllium as neutron multiplier, and reduced activat on ferritic steel F82H simulating structural material. The objective of the experiments is the neutronics performance evaluation of candidate materials for fusion reactor designs as well as the validation of neutron transport code and available neutron data libraries for these materials. A method for the dirr:ct measurement of the produced tritium based on liquids cintillation counting was developed. The activation of chromium, tungsten, and iron in F82H steel and titanium in lithium titanate was measured. Keywords: advanced breeder material, lithium titanate, thermal blanket, tritium breeding rati