#!/bin/python3 import openmc ############ MATERIALS ############ # All materials are specified in the report on HEAT PIPE MICROREACTOR MODELING WITH BLUECRAB # # Materials marked PNNL-15870 are from the 2nd revision of the report "Compendium of Material # Composition Data for Radiation Transport Modeling " by US Dept. of Homeland Security and PNNL # mat_list = [] ## Matrix Graphite ## mat_graphite_matrix = openmc.Material(name="Graphite Matrix (inside/outside)") mat_graphite_matrix.add_element("C",1.0) mat_graphite_matrix.add_nuclide("B10",0.3e-6) mat_graphite_matrix.set_density("g/cc",1.806) mat_list.append(mat_graphite_matrix) ## TRISO Pins ## mat_triso_uco = openmc.Material(name="TRISO Pin UCO Kernel") mat_triso_uco.add_element("U",1.0,enrichment=19.95,enrichment_type="wo") mat_triso_uco.add_element("C",1.0) mat_triso_uco.add_element("O",1.0) mat_triso_uco.set_density("g/cc",10.744) mat_triso_uco.add_s_alpha_beta("c_Graphite") mat_list.append(mat_triso_uco) mat_triso_buffer = openmc.Material(name="TRISO Pin Buffer") mat_triso_buffer.add_element("C",1.0) mat_triso_buffer.add_s_alpha_beta("c_Graphite") mat_triso_buffer.set_density("g/cc",1.04) mat_list.append(mat_triso_buffer) mat_triso_pyc1 = openmc.Material(name="TRISO Pin PyC1") mat_triso_pyc1.add_element("C",1.0) mat_triso_pyc1.add_s_alpha_beta("c_Graphite") mat_list.append(mat_triso_pyc1) mat_triso_sic = openmc.Material(name="TRISO Pin SiC") mat_triso_sic.add_element("Si",1.0) mat_triso_sic.add_element("C",1.0) mat_triso_sic.add_s_alpha_beta("c_Graphite") mat_triso_sic.set_density("g/cc",3.171) mat_list.append(mat_triso_sic) mat_triso_pyc2 = openmc.Material(name="TRISO Pin PyC2") mat_triso_pyc2.add_element("C",1.0) mat_triso_pyc2.add_s_alpha_beta("c_Graphite") mat_triso_pyc2.set_density("g/cc",1.882) mat_list.append(mat_triso_pyc2) ## Moderator Pins ## mat_mod_helium = openmc.Material(name="Moderator Pin Helium") mat_mod_helium.add_element("He",1.0) mat_mod_helium.set_density("g/cc",0.18e-3) mat_list.append(mat_mod_helium) mat_mod_ss316 = openmc.Material(name="Moderator Pin SS316") mat_mod_ss316.add_element("C",0.000800,"wo") mat_mod_ss316.add_element("Mn",0.020000,"wo") mat_mod_ss316.add_element("P",0.000450,"wo") mat_mod_ss316.add_element("S",0.000300,"wo") mat_mod_ss316.add_element("Si",0.010000,"wo") mat_mod_ss316.add_element("Cr",0.170000,"wo") mat_mod_ss316.add_element("Ni",0.120000,"wo") mat_mod_ss316.add_element("Mo",0.025000,"wo") mat_mod_ss316.add_element("Fe",0.653450,"wo") mat_mod_ss316.set_density("g/cc",7.67) mat_list.append(mat_mod_ss316) mat_mod_yh2 = openmc.Material(name="Moderater Pin YH2") mat_mod_yh2.add_element("Y",1.0) mat_mod_yh2.add_element("H",2.0) mat_mod_yh2.add_s_alpha_beta("c_H_YH2") mat_mod_yh2.set_density("g/cc",4.3) mat_list.append(mat_mod_yh2) ## Heat Pipes ## mat_pipe_helium = openmc.Material(name="Heat Pipe Helium") mat_pipe_helium.add_element("He",1.0) mat_pipe_helium.set_density("g/cc",0.18e-3) mat_list.append(mat_pipe_helium) mat_pipe_ss316 = openmc.Material(name="Heat Pipe SS316") mat_pipe_ss316.add_element("C",0.000800,"wo") mat_pipe_ss316.add_element("Mn",0.020000,"wo") mat_pipe_ss316.add_element("P",0.000450,"wo") mat_pipe_ss316.add_element("S",0.000300,"wo") mat_pipe_ss316.add_element("Si",0.010000,"wo") mat_pipe_ss316.add_element("Cr",0.170000,"wo") mat_pipe_ss316.add_element("Ni",0.120000,"wo") mat_pipe_ss316.add_element("Mo",0.025000,"wo") mat_pipe_ss316.add_element("Fe",0.653450,"wo") mat_pipe_ss316.set_density("g/cc",7.67) mat_list.append(mat_pipe_ss316) mat_pipe_k_liquid = openmc.Material(name="Heat Pipe Potassium (Liquid)") mat_pipe_k_liquid.add_element("K",1.0) mat_pipe_k_liquid.set_density("g/cc",0.705) mat_list.append(mat_pipe_k_liquid) mat_pipe_wick = openmc.Material.mix_materials( name = "Heat Pipe Wick", materials = [mat_pipe_k_liquid, mat_pipe_ss316], fracs = [0.7, 0.3], percent_type = 'vo' ) mat_list.append(mat_pipe_wick) mat_pipe_k_gas = openmc.Material(name="Heat Pipe Potassium (Gaseous)") mat_pipe_k_gas.add_element("K",1.0) mat_pipe_k_gas.set_density("g/cc",1.11e-4) mat_list.append(mat_pipe_k_gas) ## Export ## materials = openmc.Materials(mat_list) materials.export_to_xml() ############ GEOMETRY ############ ############ SETTINGS ############