The JENDL Dosimetry File, which contains 67 dosimetry reactions, has been revised by the Dosimetry Integral Test Working Group of the Japanese Nuclear Data Committee. Thirty-one cross sections and their covariance data were simultaneously evaluated mainly through a generalized least-squares code using the experimental data in EXFOR. In order to confirm the reliability of the present revised data, integral tests have been carried out by comparing the calculated spectrum-averaged cross sections with the measured ones in fission neutron fields, fast/thermal reactor neutron fields, D-T and D-Li fusion-like neutron fields. In most of the dosimetry cross sections, it has been found that the ratios of calculated to experimental results on their integral tests show reasonable agreement within predicted uncertainty, while unreasonable discrepancies are still observed in some revised JENDL dosimetry cross sections.