More accurately simulate the neutron flux profile - #3653
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OceanNuclear wants to merge 177 commits into
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Codecov Report❌ Patch coverage is
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## main #3653 +/- ##
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+ Coverage 47.81% 50.19% +2.37%
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Files 143 154 +11
Lines 29993 31115 +1122
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+ Hits 14342 15618 +1276
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je-cook
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March 23, 2026 09:58
…ng the strength of the macroscopic (self and other) scattering matrix.
…(...)), instead of using complex number to cover both +ve and -ve sign in the sqrt.
…esmos). Next step is to write the program for solving multi-group fluxes.
…e basically one-line alias of _groupwise_cs_value/differential_in_layer. Hence they're deleted and replaced with the appropriate terms.
…ve 'basis_group'; fixed some typing of npt.NDArray[float] to npt.NDArray[np.float64], tidied one docstring.
… the upscattering being present.
…when there is upscatter.
…the scope of 'NeutronProfile.solve_group_n' to a persistent attribute inside MaterialInfo, and renamed 'conversion_factor'. Also created NeutronProfile.extended_boundary statically as an array, rather than using AutoPopulatingDict.
…ed as a static value, rather than a property. The warning for any collision in characteristic lengths between groups is ported to inside the data.py file as well. Used sigma_source in base.py.
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…ot of the complexity associated with the AutoPopulatingDict/LayerSpecificGroupwiseConstants classes. Amended tests as well.
…ntly and has less complexity.
…e code complexity, and increasing backwards compatibility as preserve_whitespace was not an argument before tabulate version 0.10.0.
…arbitrary dimensions of c_va/s_val, c_int/s_int, c_diff/s_diff.
…of the summations handled with less redundancy & more automatically.
…g the summation inside the same block.
… by turning fsum back to np.sum (which is also useful in preparation for the next commit).
…sholds scaled by the total neutron flux/local neutron flux and currents for flagging nonconvergence at the end of solve_group_n, since the current scheme causes a lot of unnecessary warnings being raised when the flux is large.
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Description
Calculates the neutron flux profile in the first wall and blanket, using an extremely simplified diffusion-based model of an infinite slab sandwich.
Reason for choosing this model
It's better than not having a neutronics model.
It's also very simplified, so it can be calculated on the fly, without installing any deterministic neutron transport codes as dependency.
Checklist
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