Development and application of SANPR with coupling numerical methods for analysis of effect of moving condition on natural circulation of nuclear power system.

• Different numerical methods were designed for thermal-hydraulic analysis. • A self-developed program for analysis of nuclear power system was established. • The developed program was validated in several ways. • Three typical moving conditions were simulated and their effect was summarized. Because of the superior endurance, nuclear power has been paid more and more attention. In this article, different numerical methods were adopted to analysis thermal-hydraulic characteristics of nuclear power system under moving condition. A coupling strategy and optimal scheme of numerical calculation were designed to ensure accuracy and efficiency of computing. Based on designed theoretical model and numerical method, a self-developed program, SANPR, for analysis of moving condition effects on thermal-hydraulic characteristics of nuclear power system in civilian ship was established. Validation of core physics calculation, fuel heat conduction, system thermal hydraulic was done and the result shows that the program is able to make good prediction about natural circulation behaviour of nuclear power system under moving condition. Finally, three typical moving conditions were simulated and their effects on a designed nuclear power system was summarized. [ABSTRACT FROM AUTHOR]