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Next: File names Up: Neutronics program input/output Previous: Syntax of input file   Contents   Index


Syntax for cross section files

To perform the neutronics calculation for the reactor with the geometry given previously by Figure 1.5 we need the following cross sections

.
Cross sections for the bottom reflector for a given mean moderator temperature and pressure.
.
Cross sections for the core plate for a give mean temperature.
.
Cross sections as a function of both mean fuel temperature, $\mbox{T}_f$, and void fraction, $<\alpha>$, for the reactor core.
.
Cross section as a function of mean void fraction, $<\alpha>$, for the top reflector.



 
 
 
 
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