openmc-plasma-source
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Allowing blended fuel sources
Currently just 'DD' or 'DT' sources are allowed using the fuel: str = "DT", argument
We could add sources that have a fraction of DT and a different fraction of DD with a more flexible input for fuel.
How about fuel also accepts a list of tuples, where the first entry is 'DD' or 'DT' and the second entry is the relative strength
fuel = [('DD', 0.1, ('DT',0.90)]
or is a dictionary better
fuel = {'DD':0.1, 'DT':0.9}
or a proportion of D and T?
fuel = {"D": 0.5, "T":0.5}
fuel = {"D": 0.25, "T": 0.75}
That would be cool. It would need to have the reaction rate equation built in to find the relative rates of neutron energies
We could make use of equations in the Bosch and Hale paper https://iopscience.iop.org/article/10.1088/0029-5515/32/4/I07
Or cross section data, which is nicely plotted in this blog post https://scipython.com/blog/nuclear-fusion-cross-sections/