Greetings dear community,
I am testing the homogenous function of “openmc.Material.mix_materials()” and comparing it with the results of manually defined mix material. and the results differ significantly.
The test is:
cube cell of 1.26 cm in length (reflective surfaces) with 2 materials:
H2O
UO2 (4.5% U235)
isotopes used
H1, H2, O16, O17, O18, U238, U234, U235 (4.5%)
all the isotopes are of natural abundance composition except U235
the first test I defined each material separately and then used the openmc function.
the second test i defined one material incorporating the composition of the two materials with updating the density, w%, a% of each isotope respective to the new state of matter as a mixture.
Results are:
OpenMC function: K = 1.43 ,
Manually: K = 1.2
am I missing something? or should I consider extra elements when defining the homogenous mixture in Openmc? or it just doesn’t run properly if I defined it manually?
I would pretty much appreciate the help.