Hi guys,
I’ve a 2 short questions related with units in milonga that I suppose Is quite straightforward to you.
1 - I’ve a 3-D problem and I would like to set up the total power of the system to scale neutron fluxes. I understand that I should set the power and eFiss XS as:
MATERIAL xxx {
eSigmaF_1=yyy eSigmaF_2=zzz }
and
power = ppp
The problem is that I cannot figure out if the if eSigmaF is really the key I should use and which units I should use
à I suppose that the units are something like (per group) Flux [n/cm2s] = Power[W/cm3] / SigmaF [1/cm] / Efiss [J/fiss] , thus Power should be in Watts and Efiss should be in W per fission (per group). Thus I’m using
eSigmaF_X = SigmaF_X [1/cm] * efiss [J/fiss] (with power in Watts).
Anyway, is there any input card reference where I could get the available options for MATERIAL, power, etc (I cannot find it in the repository)?
2-I have some doubts with the scattering matrix. I’m using the P0 condensed data for the scattering matrix, but I suppose that the self-scattering (i.e. diagonal) should be transport corrected. So I just changed to P1 for the diagonal. Nevertheless, when I change the S1.1 and S2.2 values I see no effect in keff. I’m missing something?
Thanks,
Diego
I was using SigmaA, I suppose I should use Sigma T then?
Thanks,
Diego
BTW, there is a Manual “MILONGA version 0.1 , a free nuclear reactor core analysis code”, that I can only find in scribd. Is there any other link available?
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Hi guys,
I’ve a 2 short questions related with units in milonga that I suppose Is quite straightforward to you.
1 - I’ve a 3-D problem and I would like to set up the total power of the system to scale neutron fluxes. I understand that I should set the power and eFiss XS as:
MATERIAL xxx {
eSigmaF_1=yyy eSigmaF_2=zzz }
and
power = ppp
The problem is that I cannot figure out if the if eSigmaF is really the key I should use and which units I should use
à I suppose that the units are something like (per group) Flux [n/cm2s] = Power[W/cm3] / SigmaF [1/cm] / Efiss [J/fiss] , thus Power should be in Watts and Efiss should be in W per fission (per group). Thus I’m using
eSigmaF_X = SigmaF_X [1/cm] * efiss [J/fiss] (with power in
Watts).
Anyway, is there any input card reference where I could get the available options for MATERIAL, power, etc (I cannot find it in the repository)?
2-I have some doubts with the scattering matrix. I’m using the P0 condensed data for the scattering matrix, but I suppose that the self-scattering (i.e. diagonal) should be transport corrected. So I just changed to P1 for the diagonal. Nevertheless, when I change the S1.1 and S2.2 values I see no effect in keff. I’m missing something?
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Thanks guys for all the answers!
Just a couple of comments:
1- I’ve started with a “critical” calculation for my 3x3 core. This configuration should be critical (I’m using 2 group XS obtained from the same 3D model Serpent, where I include Sa, nuSf, Diff and Scattering Matrix with P1 in the diagonal and vacuum condition in the outside). When I analyze the results I get keff 1.00917951 (+900 pcm) which is quite good, but the flux shape is quite strange (some negative values in the top/bottom, some strange results in the central zone which I cannot figure out where came from). I attach 3 plots (the geometry, the boundaries and the flux g1). Any typical hint of what I’m doing wrong?
2- Regarding the transient, my idea is just to adjust the absortion XS in the central FA as a function of time. Nevertheless I will have to depart from a critical initial state. How should I deal with that?
3- Regarding the delayed power, I cannot figure out how to deal with that. Usually total power is considered and everything is just scaled to this initial value. But that’s probable not a very good approximation.
Thanks in advance
Diego
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Thanks, I’ll check that.
Actually I changed to volumes and then I got some mismatch in faces, which could explain the issues. But no worries, I’ll fix that.
Diego
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