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Abstract: Due to the technological advancement and continuous power demand increase in the world, nuclear power plays a vital role. The concept of small modular reactor which has power generation capability less than 300MW has gained worldwide attention due to its smaller footprint, co-generation capability, nuclear core design simplicity and non-proliferation characteristics. The aim of this study is to calculate the reactivity worth for SMR by using in-house developed computer program. Two-group neutron diffusion equations have been used to calculate following parameters: material and geometrical buckling, effective multiplication factor, thermal flux, reactor core radius and height, reflector savings, volume of fuel and moderator and nuclear fuel cycle length. C++ computer program has been used to simulate the whole process by iteration technique for cylindrical core. The neutron distribution along the axial and radial direction of nuclear fuel rod has also been analyzed. Boron Carbide has been selected as control rod materials. How the neutronics parameters change with respect to time has been observed. Works are in progress to develop a complete conceptual design of a SMR which will be useful in remote areas.