Depletion module of openmc

User Support
1

What is the difference between the built-in depletion module of openmc and general programs such as origen and fispact?

2

For me one benefit of openmc depletion is that it is readily available.

Here is a post that mentions some openmc and fispact differences.

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3

Fundamentally, they both solve the Bateman equations for predicting a future material composition given an initial composition and a flux/irradiation schedule. There are some differences with respect to how the flux / cross sections are generated and used (openmc.deplete is integrated with OpenMC’s transport solver, so the data flow is automated). There are also likely many features in ORIGEN and/or FISPACT that are not present in the depletion module of OpenMC yet. Let us know if there is a particular feature in one of these other codes that you’d really like to see in OpenMC!

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4

Hi,I would like to konw whether OpenMC can do the deplete cauclation like continuous refueling and removal?

5

This sounds like the recent TransferRates capability

Here are some links to the relevant docs

https://docs.openmc.org/en/latest/methods/depletion.html?highlight=transfer#transfer-rates

https://docs.openmc.org/en/latest/pythonapi/generated/openmc.deplete.transfer_rates.TransferRates.html#openmc.deplete.transfer_rates.TransferRates

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6

Thank you for tell me this!

But this is new in 0.13.4,I’m still using 0.13.3,and 0.13.4 also not in conda-forge channel.

What should I do to get the new vision?Install OpenMC from source?

7

To install the latest development version you can take a look at this section of the install guide

https://docs.openmc.org/en/stable/quickinstall.html#installing-from-source-on-ubuntu

The only change needed would be adding a checkout line part of the way through like this

git clone --recurse-submodules https://github.com/openmc-dev/openmc.git
cd openmc
git checkout develop
mkdir build && cd build
cmake ..
make
sudo make install
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8

Thank you for your guide,I have successfully installed the new version.
And I have some questions about this.My purpose is remove FP and add fed fuel in different rate,so i make two materials:

fuel = openmc.Material(name='fuel')
fuel.temperature = 900

fuel.set_density('g/cm3',2.712206)
fuel.add_nuclide('Li7',69.9965,'ao')
fuel.add_nuclide('Li6',0.0035,'ao')
fuel.add_nuclide('Be9',18,'ao')
fuel.add_nuclide('U238',7.68e-01,'ao')
fuel.add_nuclide('U235',1.92e-01,'ao')
fuel.add_nuclide('Th232',5.1193e+00,'ao')
fuel.add_nuclide('F19',1.3000e+02,'ao')

fed_fuel = openmc.Material(name='fed_fuel')
fed_fuel.set_density('g/cm3',2)
fuel.add_nuclide('U235',20,'ao')
fuel.add_nuclide('U238',80,'ao')
fuel.add_nuclide('F19',400,'ao')

carbon = openmc.Material(name='carbon')
carbon.temperature = 900
carbon.set_density('g/cm3',1.84)
carbon.add_element('C',1.0,'ao')

the fuel is inital fuel,and fed_fuel is what I want to add into fuel .
After I instantiate TransferRates class,I should use set_transfer_rate method to specify parameter.I think for my situation,the parameter material should be fuel,and parameter destination_material I think shoud be fed_fule .Am I understanding this correctly?
I’m not sure about the mean of parameter components,may be it is element that I want to remove?
It would be great to have an example.
Thank you for your reply!

9

sorry I’ve not yet had a go with the transfer_rate method, I am sure others on the forum have, is it worth starting a new thread

10

Alright，Thank you！ :grinning:

11

Hi @jsy
Always good to check the docs, but if I understand correctly what you’re trying to do, after you’ve set up your depletion simulation, you would want to add to the integrator instance something like this:

nuclides_to_transfer = ['U235','U238','F19'] #or whatever you want to transfer
feed_rate = 0.1 #just as an example
integrator.add_transfer_rate('fed_fuel', nuclides_to_trasnfer, feed_rate, destination_material='fuel')
integrator.integrate()