Abstract

In this study, a thermal-hydraulic analysis code has been developed for primary system of the integrated small modular pressurized water reactor IRIS (International Reactor Innovative and Secure). Numerical model of the primary system has been established, and characteristics of equipment and layout are considered. The sub-channel model is used for performance analysis of hot channel in the core. In modeling of the helically coiled steam generator, effects of secondary flow inside coiled tubes are taken into account. Based on the model established, the simulation code THAS (Thermal-Hydraulic Analysis code of SMRs) has been developed. To benchmark this code, steady state performance of the system has been calculated and compared with design parameters as well as results obtained with RELAP5. Furthermore, transient performance of the system is also simulated and compared with RELAP5. The comparison presents a good agreement, which confirms simulation capacity and accuracy of the THAS code.

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