Set axis range for plots

[ondrejch]

Great work with Serpent Tools! I love it and recommend to everyone

Is there an easy way to set axis range in the plot? For instance, how to set an arbitrary X and Y ranges in your example:

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res.plot('burnup', ['absKeff', 'colKeff'])

I tried some syntax from matplotlib, but to no avail. Thanks.

[ondrejch]

It seems I figured it out. Either, while plotting, one can adjust one axis only:

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res.plot('burnup', ['absKeff', 'colKeff']).set_xlim([min,max])
res.plot('burnup', ['absKeff', 'colKeff']).set_ylim([min,max])

Or one can get the matplotlib.axes object, fix it up, and replot:

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fig=res.plot('burnup', ['absKeff', 'colKeff'])
fig.set_xlim([min,max])
fig.set_ylim([min,max])
fig.get_figure()

[ondrejch]

For some reason when the material is selected, fuel=dep.materials['fuel0'], fuel.burnup is an array full of zeros, while fuel.days has the correct array of nonzero depletion steps.

This can be fixed by fuel.data['burnup'] = dep.metadata['burnup']

[drewejohnson]

Ondrej,

Thank you for those nice words! I'm glad you find this a useful tool.

Per your first question, setting the axes limits is done through matplotlib, as you expressed. I think the second way,

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ax = r.plot('burnup', ['absKeff', 'colKeff'])
ax.set_ylim(...)
ax.set_xlim(...)

would be the best. It avoids redundant calls to the plot method.

Per the second item, this is most suspicious. Can you provide me with the following information:

• serpentTools version from "serpentTools.__version__"
• serpent version
• python version

and I will take a look. I will need some more information to try and reproduce, as I don't encounter this issue on my end (using 0.9.2).

Best regards,

Andrew

[ondrejch]

Thanks Andrew for your reply.

Serpent tools:

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In [62]: serpentTools.__version__
Out[62]: '0.9.2'

Serpent is Version 2.1.31

Python (in spyder3)

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Python 3.7.5 (default, Nov 20 2019, 09:21:52)
IPython 5.8.0 -- An enhanced Interactive Python.

[ondrejch]

Here is the example: https://msr.ne.utk.edu/~o/test_dep.m

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fd=serpentTools.read("test_dep.m")
s=fd.materials['salt']
s.plot('burnup','adens',names=['U235','Pu239'])

[drewejohnson]

Thank you for providing the test file.
If you look at the salt's burnup with

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grep MAT_salt_BURNUP test_dep.m

you see an array of zeros present in the file. This is most curious.

My best guess as to why the salt has zero burnup would be that it's specific power (MW/kgHM) is zero. The fact that the salt contains fissile isotopes which should contribute to power production and heavy metal mass would go contrary to that. I wonder if it is due to some of the MSR refueling / material inventory mechanics (assuming this is indeed an MSR model)

[ondrejch]

Interesting. The salt is burned, its volume is set, and the only processing is an off-gas. I will email Jaakko.

[Jaakko Leppänen]

Are these materials that are not part of the geometry? Could it just be that burnup is not passed with the mass flows (I can't think how it could even be calculated). Are the material densities reasonable?

[ondrejch]

Jaakko, they are a part of geometry, everything is +- reasonable. I emailed you the input file.