blob: 0a58da35143ec6fdcc9d2d48809eceb5649ee8e5 (
plain)
1
2
3
4
5
6
7
8
9
10
11
12
13
14
15
16
17
18
19
20
|
// Scilab code Exa15.1 : : Page-652 (2011)
clc; clear;
N_0_235 = 1; // Number of uranium atom
N_0_c = 10^5; // Number of graphite atoms per uranium atom
sigma_a_235 = 698; // Absorption cross section for uranium, barns
sigma_a_c = 0.003; // Absorption cross section for graphite, barns
f = N_0_235*sigma_a_235/(N_0_235*sigma_a_235+N_0_c*sigma_a_c ); // Thermal utilization factor
eta = 2.08; // Number of fast fission neutron produced
k_inf = eta*f; // Multiplication factor
L_m = 0.54; // Material length, metre
L_sqr = ((L_m)^2*(1-f)); // diffusion length, metre
tau = 0.0364; // Age of the neutron
B_sqr = 3.27; // Geometrical buckling
k_eff = round (k_inf*exp(-tau*B_sqr)/(1+L_sqr*B_sqr)); // Effective multiplication factor
N_lf = k_eff/k_inf; // Non leakage factor
lf = (1-N_lf)*100; // Leakage factor, percent
printf("\n Total leakage factor = %4.1f percent",lf)
// Result
// Total leakage factor = 31.3 percent
|
