Abstract: The deterministic code is widely used in the calculation of radiation shielding for reactors by the advantage of its computational efficiency, but its disadvantage is that the computational accuracy is highly dependent on the accuracy of the production of multigroup cross-section libraries. However, due to the fact that the energy spectrum of ADS subcritical reactors is much harder than that of critical reactors and the energy range involved is much wider, the generally used multigroup cross-section libraries are not applicable to the calculations relating to the ADS subcritical reactors. In order to apply the deterministic code to the calculations of ADS subcritical reactors, it is necessary to re-fabricate the dedicated multigroup cross sections according to the characteristics of ADS subcritical reactors. In this study, according to the energy spectrum of the ADS subcritical reactor, a neutron-photon coupled multigroup cross-section library covering neutron energy in the range of 0~200 MeV has been produced using IMPC-NP, which is based on the Monte Carlo method. In order to verify the calculation accuracy of the cross-section library, the multigroup cross-section library is provided to the deterministic code DORT to perform criticality calculation and fixed source calculation for the ADS subcritical reactor. and then the results of the calculations were compared with those of the Monte Carlo code IMPC-NP. The calculation results show that the k_eff difference between DORT and IMPC-NP is less than 100 pcm, while the neutron flux and photon flux obtained by fixed source are in good agreement. Therefore, the neutron-photon coupled multigroup cross-section library fabricated in this study has a high computational accuracy in the calculation of ADS subcritical reactor.