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#!/bin/python3
import openmc
############ MATERIALS ############
# All materials are specified in the report on HEAT PIPE MICROREACTOR MODELING WITH BLUECRAB
# <https://www.tandfonline.com/doi/full/10.1080/00295639.2024.2375175>
# 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
# <https://www.pnnl.gov/main/publications/external/technical_reports/PNNL-15870Rev2.pdf>
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 ############
# All measurements are in cm unless specified
geo_constant_pin_pitch = 2.3
geo_constant_lattice_pitch = 26.752
geo_constant_triso_radius = 1.0
geo_constant_triso_packing = 0.40
### Inidividual Pin Universes ###
## TRISO fuel kernel ##
geo_triso_spheres = [openmc.Sphere(r=rad*1e-2, x0=0.0, y0=0.0) for rad in [2.125, 3.125, 3.525, 3.875, 4.275]]
geo_triso_cells = [openmc.Cell(name="TRISO Kernel UCO",fill=mat_triso_uco,region=-geo_triso_spheres[0]),
openmc.Cell(name="TRISO Kernel Buffer",fill=mat_triso_buffer,region=+geo_triso_spheres[0]&-geo_triso_spheres[1]),
openmc.Cell(name="TRISO Kernel PyC1",fill=mat_triso_pyc1,region=+geo_triso_spheres[1]&-geo_triso_spheres[2]),
openmc.Cell(name="TRISO Kernel SiC",fill=mat_triso_sic,region=+geo_triso_spheres[2]&-geo_triso_spheres[3]),
openmc.Cell(name="TRISO Kernel PyC2",fill=mat_triso_pyc2,region=+geo_triso_spheres[3]&-geo_triso_spheres[4])]
geo_triso_universe = openmc.Universe(name="TRISO Kernel Universe",cells=geo_triso_cells)
## TRISO compact ##
## Heat Pipe ##
geo_pipe_cylinders = [openmc.ZCylinder(r=rad, x0=0.0, y0=0.0) for rad in [0.80, 0.90, 0.97, 1.05, 1.07]]
geo_pipe_cells = [openmc.Cell(name="Heat Pipe K Gas",fill=mat_pipe_k_gas,region=-geo_pipe_cylinders[0]),
openmc.Cell(name="Heat Pipe Wick",fill=mat_pipe_wick,region=+geo_pipe_cylinders[0]&-geo_pipe_cylinders[1]),
openmc.Cell(name="Heat Pipe K Layer",fill=mat_pipe_k_liquid,region=+geo_pipe_cylinders[1]&-geo_pipe_cylinders[2]),
openmc.Cell(name="Heat Pipe SS316 Envelope",fill=mat_pipe_ss316,region=+geo_pipe_cylinders[2]&-geo_pipe_cylinders[3]),
openmc.Cell(name="Heat Pipe Helium Gap",fill=mat_pipe_helium,region=+geo_pipe_cylinders[3]&-geo_pipe_cylinders[4]),
openmc.Cell(name="Heat Pipe Graphite Matrix",fill=mat_graphite_matrix,region=+geo_pipe_cylinders[4])]
geo_pipe_universe = openmc.Universe(name="Heat Pipe Universe",cells=geo_pipe_cells)
## Moderator Pin ##
geo_mod_cylinders = [openmc.ZCylinder(r=rad, x0=0.0, y0=0.0) for rad in [0.825, 0.875, 0.900, 0.920]]
geo_mod_cells = [openmc.Cell(name="Moderator Pin YH2",fill=mat_mod_yh2,region=-geo_mod_cylinders[0]),
openmc.Cell(name="Moderator Pin Inner Helium Gap",fill=mat_mod_helium,region=+geo_mod_cylinders[0]&-geo_mod_cylinders[1]),
openmc.Cell(name="Moderator Pin SS316 Envelope",fill=mat_mod_ss316,region=+geo_mod_cylinders[1]&-geo_mod_cylinders[2]),
openmc.Cell(name="Moderator Pin Outer Helium Gap",fill=mat_mod_helium,region=+geo_mod_cylinders[2]&-geo_mod_cylinders[3]),
openmc.Cell(name="Moderator Pin Graphite Matrix",fill=mat_graphite_matrix,region=+geo_mod_cylinders[3])]
geo_mod_universe = openmc.Universe(name="Moderator Pin Universe",cells=geo_mod_cells)
### Assembly-level Geometry ###
############ SETTINGS ############
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