Abstract: The Monte Carlo method is one of the commonly used methods in reactor physics calculations. The accuracy of the continuous-energy pointwise cross-section library in ACE format adopted by Monte Carlo codes such as MCNP and RMC directly affects the transport calculation results. Therefore, it is crucial to develop a code that can accurately generate the ACE format database. Based on the independently developed nuclear data processing code Ruler, an ACE format data generation module named ACEOutput is developed in this paper, which can convert nuclear data in ENDF format into ACE format data. To verify the correctness of the neutron ACE library production function of the Ruler code, representative nuclides selected are processed into ACE format data by Ruler and NJOY2016 respectively, and the results are compared graphically. The maximum relative deviation of the cumulative probability density calculated by the two codes is less than 0.2%. In addition, CENDL-3.2 and ENDF/B-VIII.1 are processed into ACE libraries by Ruler and NJOY2016 respectively, and 2237 benchmark problems in ICSBEP are calculated. The results show that Ruler has the same accuracy as NJOY2016.