Created
April 25, 2016 02:15
-
-
Save geoffmomin/7530bdfa79955a597b2dcb03ac248b8b to your computer and use it in GitHub Desktop.
This simple MATLAB script evaluates the macroscopic cross section of fission for fuels containing uranium, oxygen, and zirconium. Enrichment percent can be defined as needed.
This file contains bidirectional Unicode text that may be interpreted or compiled differently than what appears below. To review, open the file in an editor that reveals hidden Unicode characters.
Learn more about bidirectional Unicode characters
% CANDU UO2 VERSUS LIGHTBRIDGE U-50Zr | |
% This script evaluates the macroscopic cross section of fission for fuels | |
% containing uranium, oxygen, and zirconium. Enrichment percent can be | |
% defined as needed. | |
% Developed by Geoffrey Momin | |
% This version does not require Data Table.csv | |
% ********Updates******** | |
% March 1, 2016 - 0.1 - Release | |
% - 0.2 - Prompts added to allow user fuel modification | |
% - 0.3 - Automatically solves for UO2, U-50Zr or Custom mix | |
% - 0.4 - Solves for power released in the reactor in MW/cm3 | |
% Define the values for the molar masses, avogadro's | |
% number, and microscopic cross section of fission for U235 neutrons. | |
M_U235 = 235.043923062; | |
M_U238 = 238.050782583; | |
M_O = 15.9994; | |
M_Zr = 105.93591; | |
A = 6.022*10^23; | |
micro_fission = 582.6*10^-24; | |
neutrons = 143; | |
flux = 10^14; | |
fissions_wattsec = 3.12*10^10; | |
prompt = 'Please enter either UO2, U-50Zr, or Custom: '; | |
answer = input(prompt); | |
if strcmpi(answer,'uo2') | |
p_U235 = 0.0072; | |
p_Zr = 0; | |
n_O = 2; | |
elseif strcmpi(answer,'u-50zr') | |
p_U235 = 0.197; | |
p_Zr = 0.5; | |
n_O = 0; | |
else | |
prompt = 'Please enter the enrichment percentage: '; | |
p_U235 = input(prompt)/100; | |
prompt = 'Please enter the Zirconium concentration in %wt: '; | |
p_Zr = input(prompt)/100; | |
prompt = 'Please enter the number of moles of oxygen present: '; | |
n_O = input(prompt); | |
end | |
p_U238 = 1 - p_U235 - p_Zr; | |
if p_Zr > 0 | |
density = 9.84; | |
else | |
density = 10.96; | |
end | |
mole_weight = 1/((p_U235/M_U235)+(p_U238/M_U238)); | |
enrich_density = mole_weight/(mole_weight + (n_O*M_O)+(p_Zr*M_Zr)); | |
N = ((p_U235*density*A)/(M_U235))*enrich_density; | |
macro_fission = N * micro_fission; | |
P = macro_fission*flux/fissions_wattsec; | |
fprintf('The macroscopic cross section of fission of U235 in %s is %f\n', answer, macro_fission); | |
fprintf('The maximum power output of the %s fuel in MW/cm3 is %f', answer, P); |
Sign up for free
to join this conversation on GitHub.
Already have an account?
Sign in to comment