From cbb0ee9964b081d8a4686fceaa265a550036d693 Mon Sep 17 00:00:00 2001 From: Olek <45364492+yardasol@users.noreply.github.com> Date: Wed, 3 Aug 2022 16:45:25 -0500 Subject: [PATCH] Apply suggestions from code review Co-authored-by: Paul Romano --- openmc/deplete/microxs.py | 5 ++--- 1 file changed, 2 insertions(+), 3 deletions(-) diff --git a/openmc/deplete/microxs.py b/openmc/deplete/microxs.py index 09de090bf..75058fce0 100644 --- a/openmc/deplete/microxs.py +++ b/openmc/deplete/microxs.py @@ -72,7 +72,6 @@ class MicroXS(DataFrame): reactions, diluted_materials = cls._add_dilute_nuclides(chain_file, model, dilute_initial) - diluted_materials.export_to_xml('diluted_materials.xml') model.materials = diluted_materials for rxn in reactions: @@ -113,12 +112,12 @@ class MicroXS(DataFrame): cross_sections = _find_cross_sections(model) nuclides_with_data = cls._get_nuclides_with_data(cross_sections) burnable_nucs = [nuc.name for nuc in chain.nuclides - if nuc.name in nuclides_with_data] + if nuc.name in nuclides_with_data] diluted_materials = Materials() for material in model.materials: if material.depletable: nuc_densities = material.get_nuclide_atom_densities() - dilute_density = 1.E-24 * dilute_initial + dilute_density = 1.e-24 * dilute_initial material.set_density('sum') for nuc, density in nuc_densities.items(): material.remove_nuclide(nuc)