Source rate normalization

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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.

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Jaakko Leppänen
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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

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