An intense epithermal neutron flux is necessary for boron neutron capture therapy (BNCT), a promising technique for the treatment of malignant tumors. The epithermal neutron flux is an essential characteristic of the BNCT neutron beam, and its measurement is directly related to the reliability of the treatment planning system. Such a tool could be a cylindrical activation detector using 71Ga (n,γ)72Ga reaction. In the detector, the activation material is positioned in the geometrical center of a cylinder moderator covered with cadmium foil. Two different teams of researchers calculated the sensitivities of detectors of the same size, but with different moderators which differ by a factor of 1.6. In this work, the effect of the moderator material on the sensitivity of the detector was experimentally studied.