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fusion-energy / inertial_fusion_openmc_dagmc_paramak_example

A minimal example implementation of an open source method of making DAGMC geometry with Paramak and simulating tritium production with OpenMC
MIT License
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Question about using Deuterium over Tritium? #13

Open btedman opened 7 months ago

btedman commented 7 months ago

My project uses a spherical IEC reactor with a Deuterium fuel. Is there a way to replace the existing code so as to instantiate this?

shimwell commented 7 months ago

Current the example has a 14MeV source https://github.com/fusion-energy/inertial_fusion_openmc_dagmc_paramak_example/blob/6d710616634f2430820a60363f54a26e21a80657/2_run_openmc_dagmc_simulation.py#L67 You can replace with with a 2.5MeV source

my_source.energy = openmc.stats.Discrete([2.5e6], [1])

Or you can do something better with the openmc.stats.muir distribution

my_source.energy = openmc.stats.muir(e0=2500000.0, m_rat=4.0, kt=20000.0)

I can offer more complex mixed sources if that helps

btedman commented 7 months ago

When you mention the source, are you referring to the electric potential generated, modelled as a point source, or discrete ions? Is this how you recommend implementing Deuterium over Tritium?

btedman commented 7 months ago

Essentially, my team has a spherical IEC device, and we use a deuterium fuel. I am curious if there are ways to modify the existing code to reflect our specific reactor shape, fuel source, and operating values (i.e. voltage, pressure, temp)? We need to develop a simulation model and submit results to our national board in order to gain experimental approval.

btedman commented 7 months ago

And we are specifically looking to model the Bremsstrahlung radiation/ X-Ray Emission?

shimwell commented 7 months ago

When you mention the source, are you referring to the electric potential generated, modelled as a point source, or discrete ions? Is this how you recommend implementing Deuterium over Tritium?

openmc can offer photon or neutrons for the source term. The code is a monte carlo particle transport code and doesn't know about electric potential. To change the code to model neutrons from DD instead of neutrons from DT then you can simple change the neutron energy from 14MeV to 2.5MeV

shimwell commented 7 months ago

Essentially, my team has a spherical IEC device, and we use a deuterium fuel. I am curious if there are ways to modify the existing code to reflect our specific reactor shape, fuel source, and operating values (i.e. voltage, pressure, temp)? We need to develop a simulation model and submit results to our national board in order to gain experimental approval.

Yes OpenMC and DAGMC can support different geometry types. Perhaps have a look at the documentation https://docs.openmc.org/en/stable/usersguide/geometry.html

shimwell commented 7 months ago

And we are specifically looking to model the Bremsstrahlung radiation/ X-Ray Emission?

Yes openmc can simulate photons. change the my_source.particle=='photon' as it defaults to neutron