Pincell visualisation

User Support
1

why i can’t visualize the plenume and the top or bottom nozzle here

from math import log10
import openmc.mgxs
from IPython.display import Image
import numpy as np
import matplotlib.pyplot as plt
import openmc

Create materials for the problem

uo2 = openmc.Material(name=‘UO2 fuel at 4.95% wt enrichment’)
uo2.set_density(‘g/cm3’, 10.53)
uo2.add_element(‘U’, 1., enrichment=4.95)
uo2.add_element(‘O’, 2.)

Create Helium gas material for fuel pin gap

helium = openmc.Material(name=‘Helium for gap’)
helium.set_density(‘g/cm3’, 0.0015981 )
helium.add_element(‘He’, 2.4044e-4)

Create air material for instrument tubes

air_instrument = openmc.Material(name=‘Air’)
air_instrument.set_density(‘g/cc’, 0.00616)
air_instrument.add_element(‘O’, 0.2095, ‘ao’)
air_instrument.add_element(‘N’, 0.7809, ‘ao’)
air_instrument.add_element(‘Ar’, 0.00933, ‘ao’)
air_instrument.add_element(‘C’, 0.00027, ‘ao’)

Create M5 alloy material

m5_niobium = 0.01 # http://publications.jrc.ec.europa.eu/repository/bitstream/JRC100644/lcna28366enn.pdf
m5_oxygen = 0.00135 # http://publications.jrc.ec.europa.eu/repository/bitstream/JRC100644/lcna28366enn.pdf
m5_density = 6.494 # 10.1039/C5DT03403E
m5_alloy = openmc.Material(name=‘M5’)
m5_alloy.add_element(‘Zr’, 1.0 - m5_niobium - m5_oxygen)
m5_alloy.add_element(‘Nb’, m5_niobium)
m5_alloy.add_element(‘O’, m5_oxygen)
m5_alloy.set_density(‘g/cm3’, m5_density)

Create inconel 718 material

inconel_718 = openmc.Material(name=‘Inconel’)
inconel_718.set_density(‘g/cc’, 8.2)
inconel_718.add_element(‘Si’, 0.0035, ‘wo’)
inconel_718.add_element(‘Cr’, 0.1896, ‘wo’)
inconel_718.add_element(‘Mn’, 0.0087, ‘wo’)
inconel_718.add_element(‘Fe’, 0.2863, ‘wo’)
inconel_718.add_element(‘Ni’, 0.5119, ‘wo’)

Create light water for coolant / moderator

coolant = openmc.Material(name=‘Coolant’)
coolant.set_density(‘g/cm3’, 0.997)
coolant.add_element(‘H’, 2.0)
coolant.add_element(‘O’, 1.0)
coolant.add_s_alpha_beta(‘c_H_in_H2O’)

Create stainless steel material

SS304 = openmc.Material(name=‘SS304’)
SS304.set_density(‘g/cc’, 8.03)
SS304.add_element(‘Si’, 0.0060, ‘wo’)
SS304.add_element(‘Cr’, 0.1900, ‘wo’)
SS304.add_element(‘Mn’, 0.0200, ‘wo’)
SS304.add_element(‘Fe’, 0.6840, ‘wo’)
SS304.add_element(‘Ni’, 0.1000, ‘wo’)

Create Ag-In-Cd control rod material

AIC= openmc.Material(name=‘Ag-In-Cd’)
AIC.set_density(‘g/cc’, 10.16)
AIC.add_element(‘Ag’, 0.80, ‘wo’)
AIC.add_element(‘In’, 0.15, ‘wo’)
AIC.add_element(‘Cd’, 0.05, ‘wo’)

Create stainless steel 302

SS302= openmc.Material(name=‘SS302’)
SS302.set_density(‘g/cm3’, 7.86)
SS302.add_element(‘Si’, 0.01, ‘wo’)
SS302.add_element(‘Cr’, 0.18, ‘wo’)
SS302.add_element(‘Mn’, 0.02, ‘wo’)
SS302.add_element(‘Fe’, 0.70, ‘wo’)
SS302.add_element(‘Ni’, 0.09, ‘wo’)

Create zircaloy 4 material

zircaloy_4 = openmc.Material(name=‘Zircaloy-4’)
zircaloy_4.set_density(‘g/cc’, 6.55)
zircaloy_4.add_element(‘O’, 0.00125, ‘wo’)
zircaloy_4.add_element(‘Cr’, 0.0010, ‘wo’)
zircaloy_4.add_element(‘Fe’, 0.0021, ‘wo’)
zircaloy_4.add_element(‘Zr’, 0.98115, ‘wo’)
zircaloy_4.add_element(‘Sn’, 0.0145, ‘wo’)

materials = openmc.Materials([uo2, helium, inconel_718, m5_alloy, coolant, SS304, SS302, zircaloy_4, AIC, air_instrument])
materials.export_to_xml()

Define problem geometry

INCHES=2.54

h_fuel=200
plenum_length = 13.4899
h_fuel_rod = 215.9
h_lower_end_cap = 1.4606
pitch = 1.2598
h_total=230

top_nozzle_height = 3.551*INCHES
top_nozzle_width = 0.25

bottom_lower_nozzle = h_fuel + plenum_length
top_lower_nozzle = bottom_lower_nozzle +top_nozzle_height

bottom_upper_nozzle = h_fuel + plenum_length
top_upper_nozzle = bottom_upper_nozzle +top_nozzle_height

Create cylindrical surfaces

fuel_or = openmc.ZCylinder(r=0.405765, name=‘Fuel OR’)
fuel_t_plan = openmc.ZPlane(z0=h_fuel/2)
fuel_b_plan = openmc.ZPlane(z0=-h_fuel/2)

clad_ir = openmc.ZCylinder( r=0.41402, name=‘Clad IR’)
clad_or = openmc.ZCylinder(r=0.47498, name=‘Clad OR’)

plenum_or = openmc.ZCylinder(r=0.06459 , name=‘Plenum OR’)
plenum_t_plan = openmc.ZPlane(z0=h_fuel+plenum_length)

top_nozzle = openmc.ZCylinder(r=top_nozzle_height /2 , name=‘Top nozzle’)
top_upper_nozzle_plane = openmc.ZPlane(z0=top_upper_nozzle )
bottom_upper_nozzle_plane = openmc.ZPlane(z0=bottom_upper_nozzle)

top_lower_nozzle_plane = openmc.ZPlane(z0= -top_lower_nozzle )
bottom_lower_nozzle_plane = openmc.ZPlane(z0= -bottom_lower_nozzle)

Create cells, mapping materials to regions

def fuel_pin():
“”“Returns a fuel pin universe.”“”
fuel_cell = openmc.Cell(name=‘Fuel’, fill=uo2, region=-fuel_or & -fuel_t_plan & +fuel_b_plan)
gap_cell = openmc.Cell(name=‘Gap’, fill=helium, region=+fuel_or & -clad_ir & -fuel_t_plan & +fuel_b_plan)
clad_cell = openmc.Cell(name=‘Clad’, fill=m5_alloy, region=+clad_ir & -clad_or& -fuel_t_plan & +fuel_b_plan)
moderator_cell = openmc.Cell(name=‘Moderator’, fill=coolant, region=+clad_or & -fuel_t_plan & +fuel_b_plan )

univ = openmc.Universe(name='Fuel Pin')
univ.add_cells([fuel_cell, gap_cell, clad_cell, moderator_cell])
return univ

def plenum():
“”“Returns a plenum part universe.”“”
plenum_cell = openmc.Cell(fill=SS302, region= -plenum_or )
pl_gap_cell = openmc.Cell(fill=helium, region= +plenum_or & -clad_ir)
pl_clad_cell = openmc.Cell(fill=m5_alloy, region=+clad_ir & -clad_or)
pl_moderator_cell = openmc.Cell(fill=coolant,region=+clad_or & +fuel_t_plan & -plenum_t_plan )

univ = openmc.Universe(name='Plenum Part')
univ.add_cells([plenum_cell, pl_gap_cell, pl_clad_cell, pl_moderator_cell])
return univ

def Top_nozzle():
“”“Returns a top nozzle part universe.”“”
t_nozz_cell = openmc.Cell(fill=SS304, region= -top_nozzle )
t_n_moderator_cell = openmc.Cell(fill=coolant,region= +top_nozzle & -top_upper_nozzle_plane & +bottom_upper_nozzle_plane )

univ = openmc.Universe(name='Top nozzle part')
univ.add_cells([t_nozz_cell, t_n_moderator_cell])
return univ

def Bot_nozzle():
“”“Returns a bot nozzle part universe.”“”
b_nozz_cell = openmc.Cell(fill=SS304, region= -top_nozzle )
b_n_moderator_cell = openmc.Cell( fill = coolant, region= +top_nozzle & +top_lower_nozzle_plane & -bottom_lower_nozzle_plane)

univ = openmc.Universe(name='Bot nozzle part')
univ.add_cells([ b_nozz_cell, b_n_moderator_cell])
return univ

def setup_root_universe():
fuel_pin_universe = fuel_pin()
plenum_universe = plenum()
top_nozzle_universe = Top_nozzle()
bot_nozzle_universe = Bot_nozzle()

container_universe = openmc.Universe(name='Container Universe')
fuel_pin_cell = openmc.Cell(name='Fuel Pin Cell', fill=fuel_pin_universe)
plenum_cell = openmc.Cell(name='Plenum Cell', fill=plenum_universe)
T_noz_cell = openmc.Cell(name='Top nozzle', fill=top_nozzle_universe)
B_noz_cell = openmc.Cell(name='Bot nozzle', fill=bot_nozzle_universe)

container_universe.add_cells([fuel_pin_cell, plenum_cell, T_noz_cell,  B_noz_cell])

root_cell = openmc.Cell(name='Root Cell', fill=container_universe)

# Boundary planes
min_x = openmc.XPlane(x0=-pitch/2, boundary_type='reflective')
max_x = openmc.XPlane(x0=pitch/2, boundary_type='reflective')
min_y = openmc.YPlane(y0=-pitch/2, boundary_type='reflective')
max_y = openmc.YPlane(y0=pitch/2, boundary_type='reflective')
min_z = openmc.ZPlane(z0=-300/2, boundary_type='reflective')
max_z = openmc.ZPlane(z0=300/2, boundary_type='reflective')

root_cell.region = +min_x & -max_x & +min_y & -max_y & +min_z & -max_z

root_universe = openmc.Universe(name='Root Universe')
root_universe.add_cell(root_cell)

geometry = openmc.Geometry(root_universe)
geometry.export_to_xml()

setup_root_universe()

##################################################################################################

Plot in the XY-plane

plot_xy = openmc.Plot()
plot_xy.filename = ‘plot_xy’
plot_xy.origin = [0, 0, 0] # Centered at the origin
plot_xy.width = [pitch, pitch] # Width in X and Y
plot_xy.pixels = [200, 200]
plot_xy.basis = ‘xy’
plot_xy.color_by = ‘material’
plot_xy.colors = {uo2: ‘yellow’, coolant: ‘blue’, helium:‘pink’ , SS302:‘red’}

Plot in the XZ-plane

plot_xz = openmc.Plot()
plot_xz.filename = ‘plot_xz’
plot_xz.origin = [0, 0, -35] # Centered along the XZ-plane at y=0
plot_xz.width = [2, 350] # Width in X and Z
plot_xz.pixels = [200, 2000]
plot_xz.basis = ‘xz’
plot_xz.color_by = ‘material’
plot_xz.colors = {uo2: ‘yellow’, coolant: ‘blue’,helium:‘pink’ , SS302:‘red’}

Plot in the YZ-plane

plot_yz = openmc.Plot()
plot_yz.filename = ‘plot_yz’
plot_yz.origin = [0, 0, -35]
plot_yz.width = [2., 350]
plot_yz.basis = ‘yz’
plot_yz.pixels = [200, 2000]
plot_yz.color_by = ‘material’
plot_yz.colors = {uo2: ‘yellow’, coolant: ‘blue’, helium:‘pink’ , SS302:‘red’}

Instantiate a Plots collection, add plots, and export to XML

plot_file = openmc.Plots([plot_xy, plot_xz, plot_yz])
plot_file.export_to_xml()

openmc.plot_inline(plot_file)

settings = openmc.Settings()
settings.batches = 100
settings.inactive = 10
settings.particles = 1000

Create an initial uniform spatial source distribution over fissionable zones

lower_left = (-pitch/2, -pitch/2, -1)
upper_right = (pitch/2, pitch/2, 1)
uniform_dist = openmc.stats.Box(lower_left, upper_right, only_fissionable=True)
settings.source = openmc.IndependentSource(space=uniform_dist)
settings.export_to_xml()

2

Not sure if this will answer your question, Im exclusively looking at the plotting portion of the code and im not sure what the output of this is (If this doesnt answer your question, you could add an attachment to show)

The origin is the middle of your plot, so if you wanted a topdown slice of the bottom nozzle you would have to adjust the z axis (for example).

I tend to try remove ambiguity for my width and just use (same principle can be applied for the origin):

bbox = geometry.bounding_box
plot_xy.width = (
    bbox [1][0] - bbox [0][0],
    bbox [1][1] - bbox [0][1],
)

Then just change the index as you need to. However, I dont see anything glaringly wrong with the plotting part of the code