Abstract: According to the calculation requirement of fusion-fission hybrid reactors and the relevant studies,a new 187-group constants library has been developed.This library containing more than 100 nuclides with basic data selected from ENDF/B-VI.8 can be used to calculate the neutron transport equation.The weight flux,group structures,thermal neutron transport and the Bondarenko option is considered during the process.Some calculations and comparative analyses are performed based on a series of existing benchmark experiments using ANISN.The result indicates that the library satisfies the basic requirements on calculation for designing the hybrid energy reactors.