Get U233 atom density from depletion

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1

Hi everyone,

I’m trying to deplete the SFR reactor core. However, I found an oddity when I wanted to display U233 data. I took data from all fuel materials which amounted to 15 fuels. In the fuel with id = 2, the atomic density value is very different from the other 14 data. I am running a program with 10,000 particles 100 batches and 20 inactives with PredictorIntegrator. Could you help me to understand the data?
materials.xml (23.6 KB)

u233 foto
u233 foto1599×1186 336 KB

Thanks,
Anas

2

@anas Looking at your materials.xml file, I don’t see any reason why you should see a much higher U233 concentration in material 2 based on the material composition alone. The only thing I can think of that would result in that is if most of the flux is going to material 2. Have you checked the flux in each material for your problem?

3

Thank for your answer @paulromano,

I haven’t seen the flux of each material, can you show me how to get the flux of each material?
Do I have to use MaterialFilter on the tally I create for get material flux?

And I have another question about is there a way to directly get the concentration of a nuclide from all the materials without having to add up each of the material ids?

Thanks,
Anas

4

Yes, to get the flux in each material, you’d have a single tally with a MaterialFilter that lists each material.

There’s no function that will do this automatically, so you’d have to write a loop that goes through each material, finds the concentration of the nuclide, and appends it to a list (or whatever data structure you desire).

1 Like
5

Thanks @paulromano for your answers, its helpful for me.

Anas