<![CDATA[The Research about Pressurized Water Reactors (PWR) thermal-hydraulics analysis has been done. This reseacrh aim to solve fuel rod heat conduction equation by LU Factorization method and to get thermal-hydraulics parameters such as coolant axial temperature distribution, pressure drops, convection heat transfer coefficient, and fuel rod radial temperature distribution. Heat transfer of the reactors was assumted steady state (time independent) then obtained coolant inlet tempertaure about 300 oC, outlet temperature about 326,6 oC and convection heat transfer coefficient about 1,43 W/cm2 oC. Pressure drop by friction was 0,423 bar, pressure drop by form was 0,51 bar, pressure drop by gravity was 0,25 bar and total pressure drop was 1,183 bar. While centerline fuel obtained the maximum temperature of fuel rod about 1.589,2 oC and the lowest fuel rod temperature at cladding surface about 360,9953 oC]]>
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