Merge pull request #25 from anu1217/r2s_config

WC_Layers/Conversion_h5m.py

@@ -0,0 +1,36 @@
+import openmc
+import numpy as np
+import pymoab
+from pymoab import core, types, rng
+import matplotlib.pyplot as plt
+
+# Load the statepoint file
+sp = openmc.StatePoint("statepoint.10.h5")
+
+mb = core.Core()
+mb.load_file('OpenMC_Mesh.h5m')
+
+# Retrieve the tally
+tally = sp.get_tally(id=2)
+
+# Load the mesh
+mesh = sp.meshes[1]
+
+tally_data = tally.get_reshaped_data(value='mean')
+
+#Summing over cell filter:
+flux_spectra_on_mesh = tally_data.sum(axis=0)
+
+ebounds = tally.find_filter(openmc.EnergyFilter).bins
+
+plt.xlabel('Energy [eV]')
+plt.ylabel('Flux [n/cm^2-s]')
+plt.loglog(ebounds[:,0],flux_sum_en[0,:,0,0])
+plt.savefig("Flux_Graph.png")
+
+# get all tets from the MOAB mesh
+all_tets = mb.get_entities_by_type(0, types.MBTET)
+n_flux_tag = mb.tag_get_handle('FLUX_MESH', 175, types.MB_TYPE_DOUBLE, types.MB_TAG_DENSE, create_if_missing=True)
+mb.tag_set_data(n_flux_tag, all_tets, flux_spectra_on_mesh[:,:,0,0]) # the shape of the data will need to be checked here
+
+mb.write_file('Mesh_with_Tally.h5m')

WC_Layers/PyNE_Lib.py

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+# -*- coding: utf-8 -*-
+"""
+Created on Mon Sep  2 01:08:06 2024
+
+@author: Anupama Rajendra
+"""
+
+from pyne.material import Material
+from pyne.material_library import MaterialLibrary
+
+W=Material({"W":1})
+W.density=19.3
+Graphite=Material({"C":1})
+Graphite.density=2.62
+
+MatLib = MaterialLibrary()
+MatLib["W"]=W
+MatLib["Graphite"]=Graphite
+MatLib.write_hdf5("PyNE_Lib_WC.h5", h5_overwrite=True)

WC_Layers/config.ini

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+[general]
+# Specify whether this problem uses structured or unstructured mesh
+structured: False
+# Specify whether this problem uses sub-voxel r2s
+sub_voxel: False
+
+[step1]
+# Path to MCNP MESHTAL file containing neutron fluxes or a DAG-MCNP5
+# unstructured mesh tally .h5m file.
+meshtal: Mesh_with_Tally.h5m
+# Tally number within the meshtal file containing the fluxes for activation.
+tally_num: 2
+# The name of the tag used to store flux data on the mesh. For unstructured
+# mesh this tag must already exist within the file specified in <meshtal>.
+flux_tag: FLUX_MESH
+# Path to the DAGMC material-laden geometry file (.h5m).
+geom: DAGMC_Geometry.h5m
+# If True the fluxes in the fluxin file will be printed in the reverse
+# order of how they appear within the flux vector tag. Since MCNP and
+# the Meshtal class order fluxes from low energy to high energy, this
+# option should be true if the transmutation data being used is
+# ordered from high-energy to low-energy.
+reverse: True
+# Number of rays to fire down each mesh row in each direction to calculate
+# cell volume fractions.
+num_rays: 100
+# If true, rays will be fired down mesh rows in evenly spaced intervals.
+# In this case <num_rays> must be a perfect square. If false, rays are fired
+# down mesh rows in random intervals.
+grid: False
+
+[step2]
+# List of decays times, seperated by commas. These strings much match exactly
+# with their counterparts in the phtn_src file produced in step1. No spaces
+# should appear in this line except the space between the time and the time unit
+# for each entry.
+decay_times:24 h,2.6864e+6 s
+# The prefix of the .h5m files containing the source density distributations for
+# each decay time.
+output: source
+# The name of the output files containing the total photon source intensities for
+# each decay time
+tot_phtn_src_intensities : total_photon_source_intensities.txt