For the dosimetry of high-energy accelerator neutron sources such as spallation neutron source facilities and the International Fusion Material Irradiation Facility, a dosimetry cross section set up to 50 MeV was produced by means of integral activation experiments. Activation foil samples of Al, Mn, Fe, Co, Ni, Y, Nb, In, Tm, Au, and Bi were irradiated in d-Li and d-Be neutron fields of which maximum energy was 55 MeV, and reaction rates were measured. Cross sections for 27 dosimetry reactions including (n,n'), (n,p), (n, α) and (n,2n) through (n, 6n) reactions and neutron flux spectra at the irradiation fields were adjusted simultaneously with the SAND-II code so as to be consistent with the measured reaction rates. The adjusted cross sections were found to be consistent with each other for the typical broad neutron spectra produced by the d-Li and d-Be sources.