More accurately simulate the neutron flux profile#3653
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More accurately simulate the neutron flux profile#3653OceanNuclear wants to merge 114 commits intomainfrom
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Codecov Report❌ Patch coverage is
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## main #3653 +/- ##
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+ Coverage 45.98% 46.33% +0.35%
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Files 123 125 +2
Lines 28550 29323 +773
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+ Hits 13129 13588 +459
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…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.
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…ed classes and functions are now in neutronics_data.
…have to import openmc.
…for ease of maintenace; added tests.
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…nded_boundary, to be self-populating dictionaries (populated by solve_group_n).
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Snapshot of where I'm at before taking a break for 3 weeks: The current state of this branch is:
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…each NeutronFluxProfile.coefficient[:, n] will contain self.n_groups coefficients rather than n coefficients.
…'s coefficients (i.e. coefficients used to cancel the flux shapes contributed by other groups).
… coefficient length = total number of groups rather than the current group number.
…the programmer won't have to write them out explicitly every time.
…us layer can be written as an affine transformation in linear algebra (y = Ax+b). The method _get_propagation_matrix_and_offset_vec returns A and b. num_coef_pairs is no longer needed so is deleted.
… is recorded as a vector of Kronecka delta(n,g) * flux, where g is the group index matching the incident neutron energy.
…thand to some summations (see _summation_shorthand) for ease of maintenance.
… multi-group multi-layer model. I suspect this has to do with the negative fluxes experienced by some models.
…r message, leaving the instructions on how to perform iteration calculations in the comments.
… created without knowing the nuclear data first, *and then* knowing what isotopes' nculear data needs to be get, populate_from_nuclear_data_library() can then help backfill these values, long after the instantiation of these materials.
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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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