The LINDEN code (V1) is a subchannel analysis code developed by China Nuclear Power Technology Research Institute (CNPRI). It is used to calculate the thermal–hydraulic parameters and predict the departure of nucleate boiling ratio (DNBR) in PWR under different conditions. As for the reactor under various motion conditions including the tilting, the fluctuation and the swaying conditions, the flow and heat transfer of coolant in reactor core will be affected by reflecting as an “additional force” on the coolant. In order to develop the capability of LINDEN for simulating various motion conditions, the “additional force” is decomposed into two component forces along the axial and transverse directions of reactor core, and the axial and transverse momentum conservation equations of LINDEN are modified using the correction items derived from these two component forces. In addition, the reactor core under various motion conditions are modeled and simulated by LINDEN to verify the code calculation results. The verification results show that the channels on the left side of the tilting axis have lower outlet mass flux than the channels on the right side under the tilting conditions, and the mass flux and the DNBR distributions change with the motion of reactor core with the periodic trends under the swaying or the fluctuation conditions. These code simulation trends of LINDEN are consistent well with the theoretical trends. Therefore, it can be believed that the LINDEN code is capable to simulate thermal–hydraulic characteristics of the reactor core under various motion conditions.