Questions, comments and complaints about the User's Manual
2 posts • Page 1 of 1
Hi,everyone. I am using Serpent to calculate pin cell burnup. I want to make sure if the power density we set the value of total heating power divide by the total initial mass of fissile isotope(U233,U235,Pu238,Pu241). However, the burnstep is given by MWd/kg U. Is this "U" refer to all uranium isotopes? I am quite confused.