Materials

##DRAFTING##

A material in PINSPEC is made up of one or more isotopes. Creating a material involves initializing it and adding the isotopes. A material can be initialized with whatever name the user desires as its argument. This name will be the title to whatever plots are associated with the material. >>> mix = Material('Fuel Moderator Homogeneous Mix')

Isotopes are added to materials using the "addIsotope" function, in which isotopes are defined by the name given to them in the isotope initialization section. The relative number density (or atomic ratio) of said isotope is the second argument in the function, which is set to 1 by default when the second argument is omitted.

mix.addIsotope(o16, 1.0)
mix.addIsotope(h1, 1.0)
mix.addIsotope(u238, 0.01)
mix.addIsotope(u235, .0025)
mix.addIsotope(zr90, .16)

##Setting and Retrieving Material Properties

The density of the material is also set in this section, with the number density as the first argument in the "setDensity" function and the units as the second argument. The only units currently supported are  g/cc
`mix.setDensity(5., 'g/cc')` or 'at/cc'

##Retrieving Macroscopic Cross Sections

[Next: Regions](https://github.com/mit-crpg/PINSPEC/wiki/Regions)

[[Tutorials]]

[[Home]]