From cade109745e586e61118d10b60d0754d326ff353 Mon Sep 17 00:00:00 2001 From: guillaume Date: Mon, 2 Apr 2018 14:23:36 -0400 Subject: [PATCH] took into account PR comments, got rid of redundant exports and dictionaries --- .../python/pincell_depletion/run_depletion.py | 25 +++++-------------- 1 file changed, 6 insertions(+), 19 deletions(-) diff --git a/examples/python/pincell_depletion/run_depletion.py b/examples/python/pincell_depletion/run_depletion.py index 9d81812fe..8c12211bc 100644 --- a/examples/python/pincell_depletion/run_depletion.py +++ b/examples/python/pincell_depletion/run_depletion.py @@ -1,4 +1,5 @@ import openmc +import openmc.deplete import numpy as np ############################################################################### @@ -11,9 +12,9 @@ inactive = 10 particles = 1000 # Depletion simulation parameters -time_step = 1.*24*60*60 # s -final_time = 15.*24*60*60 # s -time_steps = np.full(np.int(final_time / time_step), time_step) +time_step = 1*24*60*60 # s +final_time = 15*24*60*60 # s +time_steps = np.full(final_time // time_step, time_step) chain_file = './chain_simple.xml' power = 174 # W/cm, for 2D simulations only (use W for 3D) @@ -32,7 +33,6 @@ uo2.depletable = True helium = openmc.Material(material_id=2, name='Helium for gap') helium.set_density('g/cm3', 0.001598) helium.add_element('He', 2.4044e-4) -helium.depletable = False zircaloy = openmc.Material(material_id=3, name='Zircaloy 4') zircaloy.set_density('g/cm3', 6.55) @@ -40,7 +40,6 @@ zircaloy.add_element('Sn', 0.014 , 'wo') zircaloy.add_element('Fe', 0.00165, 'wo') zircaloy.add_element('Cr', 0.001 , 'wo') zircaloy.add_element('Zr', 0.98335, 'wo') -zircaloy.depletable = False borated_water = openmc.Material(material_id=4, name='Borated water') borated_water.set_density('g/cm3', 0.740582) @@ -48,7 +47,6 @@ borated_water.add_element('B', 4.0e-5) borated_water.add_element('H', 5.0e-2) borated_water.add_element('O', 2.4e-2) borated_water.add_s_alpha_beta('c_H_in_H2O') -borated_water.depletable = False ############################################################################### # Exporting to OpenMC geometry.xml file @@ -92,9 +90,8 @@ root = openmc.Universe(universe_id=0, name='root universe') # Register Cells with Universe root.add_cells([fuel, gap, clad, water]) -# Instantiate a Geometry, register the root Universe, and export to XML +# Instantiate a Geometry, register the root Universe geometry = openmc.Geometry(root) -geometry.export_to_xml() ############################################################################### # Exporting to OpenMC materials.xml file @@ -107,10 +104,6 @@ area[fuel] = np.pi * fuel_or.coefficients['R'] ** 2 # Set materials volume for depletion. Set to an area for 2D simulations uo2.volume = area[fuel] -# Instantiate a Materials collection and export to XML -materials_file = openmc.Materials([uo2, helium, zircaloy, borated_water]) -materials_file.export_to_xml() - ############################################################################### # Exporting to OpenMC settings.xml file ############################################################################### @@ -131,14 +124,12 @@ entropy_mesh.lower_left = [-0.39218, -0.39218, -1.e50] entropy_mesh.upper_right = [0.39218, 0.39218, 1.e50] entropy_mesh.dimension = [10, 10, 1] settings_file.entropy_mesh = entropy_mesh -settings_file.export_to_xml() ############################################################################### # Initialize and run depletion calculation ############################################################################### op = openmc.deplete.Operator(geometry, settings_file, chain_file) -op.round_number = True # Perform simulation using the predictor algorithm openmc.deplete.integrator.predictor(op, time_steps, power) @@ -150,12 +141,8 @@ openmc.deplete.integrator.predictor(op, time_steps, power) # Open results file results = openmc.deplete.ResultsList("depletion_results.h5") -# Dictionnary of materials and burned nuclides -mat_id_to_ind = results[0].mat_to_ind -nuc_to_ind = results[0].nuc_to_ind - # Obtain K_eff as a function of time time, keff = results.get_eigenvalue() # Obtain U235 concentration as a function of time -time, n_U235 = results.get_atoms(mat_id_to_ind['1'], nuc_to_ind['U235']) +time, n_U235 = results.get_atoms('1', 'U235')