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//Electric Power Generation, Transmission and Distribution by S.N.Singh
//Publisher:PHI Learning Private Limited
//Year: 2012 ; Edition - 2
//Example 7.3
//Scilab Version : 6.0.0 ; OS : Windows
clc;
clear;
neu_absor=0.80; //Absorbed Neutrons of Uranium_235 in percentage
P=100; //Power of Uranium_235 in kW
use_energy=190; //Useful Energy of Uranium_235 in MeV
energy=use_energy*10^6*1.60*10^-19; //Fission Energy of Uranium_235 in J
fission_energy=1/energy; //Number of Fission to Produced One Joule of Energy
nuclei_power=fission_energy*3600*10^6/neu_absor; //Number of Nuclei Burnt during 1 hour per MW of Power
Mass=nuclei_power*235/(6.023*10^23); //Mass of Uranium_235 to produce required Power in g/hr
printf("\nFuel consumption of U-235 to produce 100 MW will be %.4f g/hr",Mass*100);
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