Experimental Study of Heat Transfer Analysis in Vertical Rod Bundle of Sub Channel with a Hexagonal on Small Modular Reactor
Journal Title: International Journal of Modern Engineering Research (IJMER) - Year 2015, Vol 5, Issue 3
Abstract
The ability of the fluid in taking the heat generated by the nuclear reactor fuel is one important aspect of reactor safety. These capabilities must be kept high enough to maintain integrity of the fuel cladding as inside retaining radioactive substances. Study characteristics of forced convection in the fluid water using seven vertical cylinders heated uniformly in the composition ratio of hexagons with Pitch/Diameter (P/D) at 1.58 in the hexagon-shaped shell model of the reactor core test equipment in order to obtain the correlation equation displacement convection force. In this study, the heat flux and velocity of fluid flow greatly affect the temperature of the fluid. The greater the heat flux given the fluid temperature is getting higher because of the greater heat flux on the cylinder heating the heat absorbed by the fluid is also getting bigger. Similarly, the velocity of fluid flow, increasing the velocity of the fluid flow, the smaller the fluid temperature because by increasing the velocity of fluid flow in the sub channel the heat received by the fluid on the wane led to the smaller fluid temperature. Heat transfer coefficient results obtained at a velocity flow of 0.1 m s-1 is 500 Wm-2K -1 to 23 500 Wm-2K -1 , at a velocity flow of 0.3 m s -1 is 3 100 Wm-2K -1 up to 2 800 Wm-2K -1 and in velocity flow of 0.5 m s-1 is 3 500 Wm-2K -1 to 32 500 Wm-2K -1 . In this experimental study use forced convection flow has a Reynolds number range from 3 991 to 29 537 and Graetz numbers from 1 371 to 41 244. The correlation of forced convection heat transfer as follows: Nu forced = 1.641 Gz 0.4267
Authors and Affiliations
Syawaluddin , Anwar Ilmar Ramadhan , Ery Diniardi , Erwin Dermawan , Rismansyah
Keywords
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