Source rate normalization

Questions, comments and complaints about the User's Manual
Post Reply
GangWANG
Posts: 2
Joined: Thu Apr 23, 2015 12:34 am
Security question 1: No
Security question 2: 92

Source rate normalization

Post by GangWANG » Thu Apr 23, 2015 12:58 am

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.

User avatar
Jaakko Leppänen
Site Admin
Posts: 2434
Joined: Thu Mar 18, 2010 10:43 pm
Security question 2: 0
Location: Espoo, Finland
Contact:

Re: Source rate normalization

Post by Jaakko Leppänen » Thu Apr 23, 2015 8:28 pm

It's actually per initial heavy metal, i.e. All fissile isotopes.
- Jaakko

Post Reply