Abstract: Neutron physics experiments on graphite and FLiNa salt were carried out on LR-0 of the Czech Republic to verify the physics characteristics of advanced reactor cooled by fluorine salt. Benchmarks meeting the international critical safety analysis and evaluation standard were established. CENDL-TMSR-V1, developed by China Nuclear Data Center for Th-U fuel cycle analysis, was verified by using MCNP and SCALE program against LR-0 benchmarks. The results show that the keff, energy spectrum and neutron flux in the graphite and FLiNa salt of LR-0 calculated by CENDL-TMSR-V1 agree well with the experimental results. The maximum difference of critical calculation is -0.001 87, which is within the range of experimental uncertainty. Compared with the calculation results of ENDF/BⅦ.0, the calculated values obtained by CENDL-TMSR-V1 are more close to the experimental results. The uncertainty analysis shows that the uncertainty caused by graphite and FLiNa salt data obtained from CENDL-TMSR-V1 covariance data library is significantly less than that obtained from SCALE6.1 covariance data library.