Thermal–hydraulic performance analysis of IPWR during full pressure start-up mode

Abstract

This study analyzes the structural characteristics and the dynamic performance of an integrated pressurized water reactor (IPWR). The primary loop of the reactor is relatively simplified. Thereafter a description of the system’s mathematical and physical models are established. The models of the primary loop including the core model, the simplified pump model, the once-through steam generator (OTSG), the flow friction and heat transfer models are built and then coded with Fortran 90. Meanwhile, all possible flow and heat transfer conditions are considered and the corresponding optional models are also presented. The GEAR method is adopted for the numerical solution of transient equations. The full pressure start-up mode is used to control the IPWR based on these models. The results show that the calculated parameters are in good agreement with the design values. Core inlet and outlet temperatures, OTSG secondary side temperature and pressurizer pressure are within the safety limit values, which shows that the mode of IPWR is reasonable. The proposed mode is suitable for not only the ship nuclear power systems but also the small or medium size nuclear power plants in both the economic and technological aspects. The present work provides an important theoretical basis and reference for the control strategy of an IPWR. Additionally, because of the adoption of modular programming techniques, both the steady- and transient-state analysis codes can be easily applied to other thermal–hydraulic analyses of special reactors and special cases by modifying and updating the corresponding function modules.