An integral benchmark experiment on the Lithium Fluoride (LiF) material has been carried out in order to check the accuracy of neutronic design calculations. Experimental data of the tritium production rate and the radiation heating rate have been measured directly by each technique using Lithium Carbonate (Li2CO3) pellets and LiF thermo-luminescent dosimeters (LiF-TLDs), and indirectly by the multi-activation foil technique. The present accuracies of the neutronic calculations on the tritium breeding and the nuclear heating are discussed through comparing these benchmark data, where the two-dimensional transport code DOT 3.5 and the ENDF/B-IV cross-section library are applied as a typical example.