reprocessing MSR using mflow

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thanusek
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reprocessing MSR using mflow

Post by thanusek » Sat Apr 11, 2020 2:18 pm

Dear Developers and Users,

I want to model online reprocessing using mflow card. There are some posts open by Gavin Ridley where he made a lot of work to progress online reprocessing. As far as I know, this option is still not working 100% correctly. I took Godiva model in order to check all options for mflow.
Using this model I check both directions of material flow: from the core to outside and from outside to the core.
In both scenarios flowing material was fuel:

Code: Select all

92235.03c -.9473 
92238.03c -.0527 


Here is my input file:

Code: Select all

set title "Godiva"

%------define the sphere's surface----

surf 1 sph 0 0 0 8.7407
surf 2 sph 0 0 0 15.0

%------define cells--------------------

cell 1 0 uranium -1
cell 2 0 refl   1 -2
cell 3 0 outside 2

%-------material definition--------------

mat uranium -14.2  burn 1 vol 2797.224046 %18.74 g/cm^3
92235.03c -.9473 
92238.03c -.0527  

% outside, source of fuel inflow
mat sourceSolution  -14.2    burn 1   vol 2797.0
92235.03c -.9473 
92238.03c -.0527

mat refl -1.0  burn 1 vol 11339.94289505627
1001.03c .667
8016.03c .333

%-------criticality calculation settings---------

set pop 10000 200 100 %1000 neutrons, 110 cycles, 10 of them inactive
set gcu -1


%-------Set the xs library locations-------------

set acelib   "/mnt/opt/apps/slc6/serpent/2.1-x86_64-gcc48-openmpi110/xsdata/sss_jeff311u.xsdata"  "/mnt/opt/apps/slc6/serpent/2.1-x86_64-gcc48-openmpi110/xsdata/photoatomic1.xsdata" 
set declib "/mnt/opt/apps/slc6/serpent/2.1-x86_64-gcc48-openmpi110/xsdata/endfb7/sss_endfb7.dec"
%set sfylib "/mnt/opt/apps/slc6/serpent/2.1-x86_64-gcc48-openmpi110/xsdata/endfb7/sss_endfb7u.sfy"
set pdatadir "/mnt/opt/apps/slc6/serpent/2.1-x86_64-gcc48-openmpi110/xsdata/photon_data_2.1.30"
set nfylib "/mnt/opt/apps/slc6/serpent/2.1-x86_64-gcc48-openmpi110/xsdata/endfb7/sss_endfb7.nfy"


set power 1
set pcc 0 %to match the other refueling file, turn pcc off


mflow FlowingRatio
all 0.000003237527831


rep myreprocess
rc sourceSolution uranium      FlowingRatio 2

set depmtx 1

dep pro myreprocess
daystep
0.3
0.3
0.3
0.3
0.3
0.3
0.3
0.3
0.3
0.3
0.3
In this input configuration, fuel is going from outside to the core. In the opposite situation, I just replace the order of material in rc card.

I made simulations for options 0,1 and 2. To have reference data, I made also criticality simulations, where I was changing the density of fuel gradually, to have the same amount of material as in burnup mode. This is why, the power is just 1 watt - to not loose material during burnup.

Image
Image
Image

It looks like this:
For feeding the core, options 1 and 2 working exponentially, for option 0 it is a constant flow and it matches the results for criticality simulation.

For taking fuel out of the core, in version 2.1.30 and 2.1.31 option 0 is not working, option 2 and 1 works exponentially.
So, in my opinion, the only problem is none of the options is working as a constant flow when we want to take out some material.

I do not know what is now status the mflow option for Serpent 2. I hope it can somehow help you.

I have also an idea and a question. If the development of online reprocessing is still far away from the final shape, maybe users can use the restart file?

As far as I know, restart file store not only transport nuclides, but also decay isotopes. Unfortunately, it is a binary form. How we can decode it, to be able to change the densities of specifics isotopes (using a script probably)?

All the best,

Tomasz

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