In the paper the multi-nodal Pressurized Water Reactor (PWR) heat transfer model based on Mann's model is presented. This model is used for heat transfer from fuel to coolant modelling purposes in a reactor core. The authors expand the approach widely used in literature by defining additional coefficients for heat transfer model. These parameters approximate the power generation distribution in the PWR reactor core according to the reactor control rod bank movement. Authors describe in details the proposed methodology for calculation of introduced power distribution coefficients. In the simplest case, those coefficients may be equal and constant over time and space of a reactor. On the other hand, they can be treated as variables that are time and reactor region dependent. By introducing these specific coefficients, the nodal model of heat transfer gains advanced capabilities that can be efficiently used in design and synthesis of more advanced and complex power control system in nuclear reactor with respect to temperature distribution within the reactor core.