More accurately simulate the neutron flux profile #3653
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## main #3653 +/- ##
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- Coverage 45.98% 42.77% -3.22%
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Files 123 125 +2
Lines 28550 38543 +9993
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+ Hits 13129 16486 +3357
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chris-ashe
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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).
…d populated the docstring of NeutronFluxProfile.
…of commits ago (because I was in a hurry) in groupwise_neutron_current_through_interface
…nup successful: unit test and regression test (1-group regression test case only) passed. Only the plotting function remains to be fixed for this conversion to infinite-layer model.
…haviour of (NeutronFluxProfile.coefficients, NeutronFluxProfile.l2, NeutronFluxProfile.diffusion_const)
…aries (i.e. interfaces) are properly drawn. Will need to make heating calculation method.
…r both flux and current, but not for heating yet.
…its from eV to Joule
…so they're still valid under the new units (J, instead of eV)
…iscontinuity present are all justified (i.e. have physical meaning). This in turn updated the behaviour of some methods, and notably two new methods are added to calculate the heating in a per-layer fashion. Docstring updates as well.
… exist without first re-writing solve_lowest_group
…p while keeping _calculate_mean_energy_and_incident_bin as a staticmethod.
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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.
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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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