| Summary: | International Criticality Safety Benchmark Evaluation Project (ICSBEP) criticality analyses were conducted using the McCARD Monte Carlo code for 85 selected benchmark problems with 7 evaluated nuclear data libraries (ENDLs): ENDF/B-VII.1, ENDF/B-VIII.0, JENDL-4.0, JENDL-5.0, JEFF-3.3, TENDL-2021, and CENDL-3.2. Regarding the analyses, it was confirmed that the <i>k<sub>eff</sub></i> results are sensitive to the ENDL. It is noted that the new-version ENDLs show better performance in the fast benchmark cases, while on the other hand, there are no significant differences in <i>k<sub>eff</sub></i> among the different ENDLs in the thermal benchmark cases. The sensitivity of the <i>k<sub>eff</sub></i> results depending on the ENDL may impact nuclear core design parameters such as the shutdown margin, critical boron concentration, and power defects. This study and <i>k<sub>eff</sub></i> results will be a good reference in the development of new types of nuclear cores or new design codes.
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