I am performing an infinite medium criticality calculation where I define only ONE material composed of different isotopes. Since I need a very fine spectral analysis of the system, I defined the following option that prints out the <filename>_xs0.m file.
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set xsplot 7000 1.0E-05 1.0E+02
(1) Does the <isotope>_mt vector contain the ENDF reaction mode MT's? If so, since all the _mt vectors of the isotopes in my calculation starts from 2, how can I get the total cross-section (MT = 1)?
(2) Among other data, I got a vector named m<matname>_tot, with 7000 rows (n° of energy bins) and 4 columns. Can you explain the meaning of those?
Just to be clear, I want to plot the material total cross section and, if possible, the isotope total cross sections, as function of the energy.
Thank you in advance.