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Rename results.h5 -> depletion_results.h5. Use /materials in HDF5 file
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9 changed files with 11 additions and 16 deletions
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@ -8,7 +8,7 @@ from openmc.deplete import (read_results, evaluate_single_nuclide,
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result_folder = "test"
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# Load data
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results = read_results(result_folder + "/results.h5")
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results = read_results(result_folder + "/deplete_results.h5")
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cell = "5"
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nuc = "Gd157"
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@ -28,7 +28,6 @@ settings.particles = 1000
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settings.batches = 100
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settings.inactive = 40
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settings.source = openmc.Source(space=openmc.stats.Box(lower_left, upper_right))
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settings.verbosity = 3
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op = openmc.deplete.OpenMCOperator(geometry, settings)
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