Prediction of critical heat flux on surface under boiling in case of IVR-ERVC by using CFD simulation

2019 International Conference on Advances in Materials, Mechanical and Manufacturing

材料科学;机械制造

Urfa, Rasool^1 ; Lu, Daogang^1 ; Asran, Noor Farooq^2 ; Munib, Ansari^1 ; Aazim, Rasool^1

Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy, North China Electric Power University, Beijing

102206, China^1

Pakistan Institute of Engineering and Applied Sciences, Pakistan^2

关键词: CFD simulations;    Critical heat flux(CHF);    External reactor vessel cooling;    Hydraulic diameter;    Radius of curvature;    Reactor Pressure Vessel;    Spatial variations;    Square cross section;   

Others  :  https://iopscience.iop.org/article/10.1088/1757-899X/576/1/012042/pdf
DOI  :  10.1088/1757-899X/576/1/012042

学科分类：材料科学（综合）

来源: IOP

【 摘 要 】

The efficacy of in-vessel through external reactor vessel cooling (IVR-ERVC) is strongly correlated with the critical heat flux (CHF) on the lower head of reactor pressure vessel (RPV). The high limit of CHF prevents the RPV from failure by extracting much heat out of the vessel through the circulation of working fluid in external flow channel. In present study, the deionized water is allowed to flow through curved flow channel having radius of curvature of 368mm and hydraulic diameter of 40mm with square cross-section. The heat flux of 1500kWm-2 is applied perpendicular to the convex wall of the channel. The CHF on the wall of flow channel has been predicted by incorporating CFD based two-phase (liquid-vapor) boiling model. The investigations on spatial variation of pressure, temperature, and velocity and heat flux acquired as a result of numerical simulations have been discussed in detail. The CHF and average HTC is predicted as 1.798e+04kWm-2 and 38.981kWm-2K-1 respectively.