# Pincell visualisation **URL:** \ **Category:** User Support\ **Created:** [May 3, 2024, 10:19am UTC](https://openmc.discourse.group/t/pincell-visualisation/4231 "2024-05-03T10:19:56Z")\ **Posts on this page:** 2\ **Page:** 1
**Author:** ![mariemm](https://avatars.discourse-cdn.com/v4/letter/m/7cd45c/32.png) [@mariemm](https://openmc.discourse.group/u/mariemm)\ **Post date:** [May 3, 2024, 10:19am UTC](https://openmc.discourse.group/t/pincell-visualisation/4231/1 "2024-05-03T10:19:56Z")
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](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](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() ---
**Author:** ![JustAnotherNeutron](https://avatars.discourse-cdn.com/v4/letter/j/e5b9ba/32.png) [@JustAnotherNeutron](https://openmc.discourse.group/u/JustAnotherNeutron)\ **Post date:** [May 3, 2024, 10:43am UTC](https://openmc.discourse.group/t/pincell-visualisation/4231/2 "2024-05-03T10:43:25Z")
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): ```auto 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