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

Abstract 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.

[1]  G. Su,et al.  Study on safety boundary of flow instability and CHF for parallel channels in motion , 2018, Nuclear Engineering and Design.

[2]  Isao Iyori,et al.  Natural circulation characteristics of a marine reactor in rolling motion , 1990 .

[3]  Hong Zhang,et al.  Investigations on Friction Resistance of Forced Circulation in a Circular Tube Under Inclination and Rolling Conditions , 2010 .

[4]  Isao Iyori,et al.  Natural circulation of integrated-type marine reactor at inclined attitude , 1987 .

[5]  Hideki Nariai,et al.  Thermal-hydraulic behavior of a marine reactor during oscillations , 1990 .

[6]  Hiroyuki Murata,et al.  Natural circulation characteristics of a marine reactor in rolling motion and heat transfer in the core , 2002 .

[7]  Toshihisa Ishida,et al.  Effects of ship motions on natural circulation of deep sea research reactor DRX , 2002 .

[8]  G. Su,et al.  The influence of ocean conditions on thermal-hydraulic characteristics of a passive residual heat removal system , 2015 .

[9]  H Murata,et al.  STUDY ON THE NATURAL CIRCULATION OF AN INTEGRATED TYPE MARINE REACTOR AT INCLINED ATTITUDE , 1988 .

[10]  Guanghui Su,et al.  Experimental study on two-phase flow instability of natural circulation under rolling motion condition , 2009 .

[11]  L. A. Bromley.  Heat Transfer in Stable Film Boiling , 1949 .

[12]  Jianli Hao,et al.  The development of natural circulation operation support program for ship nuclear power machinery , 2012 .

[13]  S. Churchill,et al.  Correlating equations for laminar and turbulent free convection from a vertical plate , 1975 .

[14]  Arthur E. Bergles,et al.  Two-Phase Flow Heat Exchangers , 1988 .

[15]  H. Murata,et al.  Experimental Investigation of Natural Convection in a Core of a Marine Reactor in Rolling Motion , 2000 .

[16]  Weiwei Chen,et al.  Evaluation of frictional pressure drop correlations for two-phase flow in pipes , 2012 .