Cross section data plotter

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fabioalcaro
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Cross section data plotter

Post by fabioalcaro » Mon Oct 15, 2012 12:58 pm

Hi,
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
I have some questions about the arrays contained in it:
(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.

cheers
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Jaakko Leppänen
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Re: Cross section data plotter

Post by Jaakko Leppänen » Mon Oct 15, 2012 5:01 pm

1) The isotopic cross sections include all partials, with the ENDF reaction mt's listed in the mt-vector. You can get the total cross section by summing over the partials.
2) The four columns in the material-wise cross sections are the macroscopic total, total elastic, total absorption and total fission cross sections.
- Jaakko

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fabioalcaro
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Re: Cross section data plotter

Post by fabioalcaro » Mon Oct 15, 2012 6:04 pm

Thank you
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