Calculation of dosimetry parameters by TG-۶۰ approach for beta sources and TG-۴۳ approach for gamma sources can help to design brachytherapy sources. In this work, TG-۶۰ dosimetry parameters are calculated for the Sm-۱۵۳ brachytherapy seed using the Monte Carlo simulation approach. The continuous beta spectrum of Sm-۱۵۳ and probability density are applied to simulate the Sm-۱۵۳ source. Sm-۱۵۳ is produced by neutron capture during the ۱۵۲Sm( n,)۱۵۳Sm reaction in reactors. The Sm-۱۵۳ radionuclide decays by beta rays followed by gamma-ray emissions with half-life of ۱.۹۲۸ days. Sm-۱۵۳ source is simulated in a spherical water phantom to calculate the deposited energy and geometry function in the intended points. The Sm-۱۵۳ seed consists of ۲۰% samarium, ۳۰% calcium and ۵۰% silicon, in cylindrical shape with density ۱.۷۶gr/cm^۳. The anisotropy function and radial dose function were calculated at ۰-۴mm radial distances relative to the seed center and polar angles of ۰-۹۰ degrees. The results of this research are compared with the results of Taghdiri et al. (Iran. J. Radiat. Res. ۹, ۱۰۳ (۲۰۱۱)). The final beta spectrum of Sm-۱۵۳ is not considered in their work. Results show significant relative differences even up to ۵ times for anisotropy functions at ۰.۶, ۱ and ۲mm distances and some angles. MCNP۴C Monte Carlo code is applied in both in the present paper and in the above-mentioned one.