mit-crpg / OpenMOC

A method of characteristics code for nuclear reactor physics calculations.
https://mit-crpg.github.io/OpenMOC/
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A question about openmc and openmoc when used MGXS part #472

Closed liangyuxuan-08 closed 3 years ago

liangyuxuan-08 commented 3 years ago

Dear I encountered a problem like this. When I cut a small universe with a large cell, openmc can run, but the converted openmoc cannot run, and an error occurs. lat 5 is the core lattice( pitch =21.4)

xmin_1 = openmc.XPlane(x0=-117.7, name='xmin') xmax_1 = openmc.XPlane(x0= 117.7, name='xmax') ymin_1 = openmc.YPlane(y0=-117.7, name='ymin') ymax_1 = openmc.YPlane(y0= 117.7, name='ymax') zmin_1 = openmc.ZPlane(z0=-120, name='zmin') zmax_1 = openmc.ZPlane(z0= 120, name='zmax')

xmin_2 = openmc.XPlane(x0=-120, name='xmin') xmax_2 = openmc.XPlane(x0= 120, name='xmax') ymin_2 = openmc.YPlane(y0=-120, name='ymin') ymax_2 = openmc.YPlane(y0= 120, name='ymax') zmin_2 = openmc.ZPlane(z0=-122, name='zmin') zmax_2 = openmc.ZPlane(z0= 122, name='zmax')

xmin = openmc.XPlane(x0=-119, name='xmin',boundary_type='vacuum') xmax = openmc.XPlane(x0= 119, name='xmax',boundary_type='vacuum') ymin = openmc.YPlane(y0=-119, name='ymin',boundary_type='vacuum') ymax = openmc.YPlane(y0= 119, name='ymax',boundary_type='vacuum') zmin = openmc.ZPlane(z0=-121, name='zmin',boundary_type='vacuum') zmax = openmc.ZPlane(z0= 121, name='zmax',boundary_type='vacuum')

root_cell1 = openmc.Cell(cell_id=200,name = 'root cell',fill=lat5,region=+xmin_1&-xmax_1&+ymin_1&-ymax_1&+zmin_1&-zmax_1)

root_cell2 = openmc.Cell(cell_id=201,fill=water_h7,region=(~(+xmin_1&-xmax_1&+ymin_1&-ymax_1&+zmin_1&-zmax_1))&+xmin_2&-xmax_2&+ymin_2&-ymax_2&+zmin_2&-zmax_2)

core_universe = openmc.Universe(cells=[root_cell1,root_cell2])

root_cell = openmc.Cell(cell_id=206,name = 'root cell',fill=core_universe,region=+xmin&-xmax&+ymin&-ymax&+zmin&-zmax)

root_universe = openmc.Universe(cells=[root_cell])

when I used this script will report an error :Exceeded the maximum version number in 2D extruded FSRs when openmoc calculation, but openmc was ok

and I used follow script:

root_cell = openmc.Cell(cell_id=200,name = 'root cell',fill=lat5,region=+xmin&-xmax&+ymin&-ymax&+zmin&-zmax)) root_universe = openmc.Universe(cells=[root_cell])

can run in openmc and openmoc.

i want wo ask how can i solve it? thank you