[en] Study of the neutron induced reactions are of immense interest in reactor applications. Nuclear reactor consists of structural materials, control rods, fuel and shielding materials, therefore, when neutrons originated from fusion or fission reaction interact with these materials, they change mechanical and physical properties of materials. It is necessary to have cross section data for these materials at all possible neutron energies. Lots of measured experimental nuclear data is available in the EXchange FORmat (EXFOR) library. In present work, we have studied ¹⁰³Rh(n,2n)¹⁰²Rh reaction at neutron energy of 20.12±12.03. The cross section was measured using neutron activation analysis (NAA) technique. The experimentally measured neutron cross-section data is also compared with evaluated nuclear data libraries from ENDF/BVII, JEFF 3.2. The measured cross section is important to enhance the nuclear data, as well as for nuclear reactor applications