Simple umsh 8 cubes input

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Revision as of 17:35, 15 March 2016 by Ville Valtavirta (talk | contribs) (→‎./constant/polyMesh/materials file)
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Material densities at the inner region of the example geometry (red is high, blue is low).
Material temperatures at the inner region of the example geometry (red is high, blue is low).
Uranium 233 atomic densities at the inner region of the example geometry (red is high, blue is low).

These example inputs showcase the unstructured mesh based geometry and interface capabilities in Serpent 2.

The problem geometry is a cube with coordinates [-150, 150]x[-150, 150]x[-150, 150] divided into an inner region inside [-100, 100]x[-100, 100]x[-100, 100] and a blanket region.

The inner region is also evidently cube shaped but consists of 8 sub-regions:

  • Areas with positive x (+,?,?) have a larger material density (affects the nuclide densities in macroscopic cross sections).
  • Areas with positive y (?,+,?) have a larger temperature (affects the temperatures of microscopic cross sections).
  • Areas with positive z (?,?,+) have a larger U-233 content (affects the material composition).

In the following sections this geometry is created in several different ways:

  1. Using the normal Serpent geometry definitions with separate materials for all 8 regions.
  2. Using the unstructured mesh based geometry definition with separate materials for all 8 regions.
  3. Using the normal Serpent geometry definitions with temperature and density data brought in using the unstructured mesh based interface.
  4. Using the unstructured mesh based geometry definition with attached temperature and density data for the materials.

Traditional way

The "traditional" way of defining a geometry with multiple materials at multiple densities and temperatures is to create a separate material for each of the temperature and density combinations. As this example has two different nuclide compositions we end up with 23 = 8 separate materials. This input creates the geometry by splitting the inner region into eight sub-regions using the coordinate planes. The correct material is then filled into each octant. The temperature and density data are specified in the material card.

Main input file

set title "8 cubes hexahedron test, CSG geo"

% --- Boundary of geometry:

surf 2  cuboid -150 150 -150 150 -150 150

% --- Boundary at infinity

surf 3 inf

% --- yz-plane

surf yzPlane px 0.0

% --- xz-plane

surf xzPlane py 0.0

% --- xy-plane

surf xyPlane pz 0.0

% --- Cube with two metre edge length:

surf 2metreCube cuboid -100 100 -100 100 -100 100

% --- Geometry based on the normal CSG-model

cell HiHiHi 0    fuelHiDHiTHiU    yzPlane  xzPlane  xyPlane -2metreCube
cell HiLoHi 0    fuelHiDLoTHiU    yzPlane -xzPlane  xyPlane -2metreCube
cell HiHiLo 0    fuelHiDHiTLoU    yzPlane  xzPlane -xyPlane -2metreCube
cell HiLoLo 0    fuelHiDLoTLoU    yzPlane -xzPlane -xyPlane -2metreCube
cell LoHiHi 0    fuelLoDHiTHiU   -yzPlane  xzPlane  xyPlane -2metreCube
cell LoLoHi 0    fuelLoDLoTHiU   -yzPlane -xzPlane  xyPlane -2metreCube
cell LoHiLo 0    fuelLoDHiTLoU   -yzPlane  xzPlane -xyPlane -2metreCube
cell LoLoLo 0    fuelLoDLoTLoU   -yzPlane -xzPlane -xyPlane -2metreCube

% --- Blanket cell around the eight cubes

cell 11  0 blanket   2metreCube -2

% --- Outside the geometry

cell 20  0 outside    2

% --- Black BC

set bc 1

% --- Fuel salts:

% --- Material for cube at (+,+,+) corner (umsh cell 0)
mat fuelHiDHiTHiU  -4.10 tmp 1200.0
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65         
U-233.06c        2.85

% --- Material for cube at (+,-,+) corner (umsh cell 1)
mat fuelHiDLoTHiU  -4.10 tmp 600.0
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65
U-233.06c        2.85

% --- Material for cube at (+,+,-) corner (umsh cell 2)
mat fuelHiDHiTLoU  -4.10 tmp 1200.0
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65
U-233.06c        1.425

% --- Material for cube at (+,-,-) corner (umsh cell 3)
mat fuelHiDLoTLoU  -4.10 tmp 600.0
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65
U-233.06c        1.425

% --- Material for cube at (-,+,+) corner (umsh cell 4)
mat fuelLoDHiTHiU  -2.05 tmp 1200.0
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65
U-233.06c        2.85

% --- Material for cube at (-,-,+) corner (umsh cell 5)
mat fuelLoDLoTHiU  -2.05 tmp 600.0
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65
U-233.06c        2.85

% --- Material for cube at (-,+,-) corner (umsh cell 6)
mat fuelLoDHiTLoU  -2.05 tmp 1200.0
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65
U-233.06c        1.425

% --- Material for cube at (-,-,-) corner (umsh cell 7)
mat fuelLoDLoTLoU  -2.05 tmp 600.0
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65
U-233.06c        1.425

% --- Blanket material 
mat blanket     -0.10 rgb 50 250 50
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65         
U-233.06c        2.85

% --- Run parameters:

set pop 5000 200 20

% --- Geometry plot:

plot 1 500 500  10
plot 1 500 500 -10

% --- Mesh plots:

mesh 10 1 500 500
mesh 1 500 500

% --- Power level:

set power 8.0

Unstructured mesh based geometry

The geometry can be also defined using the irregular geometry card solid 1. This is of minor use here since the geometry in this case is easy to define using the normal constructive solid geometry definitions. The inner region is still created using eight separate materials but this time the geometry cells are based on the unstructured mesh definition.

Main input file

set title "8 cubes hexahedron test"

% --- Boundary of geometry:

surf 2  cuboid -150 150 -150 150 -150 150

% --- Boundary at infinity

surf 3 inf

% --- OpenFOAM mesh based geometry (universe 1, bg universe 2)
%     Search mesh split condition is 5 cells
%     Search mesh has maximum of two levels with maximum of 2^n 
%     cells per level

solid 1 1 2
5 2 2 2
"./constant/polyMesh/points"
"./constant/polyMesh/faces"
"./constant/polyMesh/owner"
"./constant/polyMesh/neighbour"
"./constant/polyMesh/materials"

% --- Blanket cell in universe 2 (background universe)

cell 11  2 blanket   -3

% --- Geometry consists of mesh-based universe and background universe

cell 19  0 fill 1    -2

% --- Outside the geometry

cell 20  0 outside    2

% --- Black BC

set bc 1

% --- Fuel salts:

% --- Material for cube at (+,+,+) corner (umsh cell 0)
mat fuelHiDHiTHiU  -4.10 tmp 1200.0
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65         
U-233.06c        2.85

% --- Material for cube at (+,-,+) corner (umsh cell 1)
mat fuelHiDLoTHiU  -4.10 tmp 600.0
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65
U-233.06c        2.85

% --- Material for cube at (+,+,-) corner (umsh cell 2)
mat fuelHiDHiTLoU  -4.10 tmp 1200.0
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65
U-233.06c        1.425

% --- Material for cube at (+,-,-) corner (umsh cell 3)
mat fuelHiDLoTLoU  -4.10 tmp 600.0
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65
U-233.06c        1.425

% --- Material for cube at (-,+,+) corner (umsh cell 4)
mat fuelLoDHiTHiU  -2.05 tmp 1200.0
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65
U-233.06c        2.85

% --- Material for cube at (-,-,+) corner (umsh cell 5)
mat fuelLoDLoTHiU  -2.05 tmp 600.0
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65
U-233.06c        2.85

% --- Material for cube at (-,+,-) corner (umsh cell 6)
mat fuelLoDHiTLoU  -2.05 tmp 1200.0
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65
U-233.06c        1.425

% --- Material for cube at (-,-,-) corner (umsh cell 7)
mat fuelLoDLoTLoU  -2.05 tmp 600.0
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65
U-233.06c        1.425

% --- Blanket material 
mat blanket     -0.10 rgb 50 250 50
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65         
U-233.06c        2.85

% --- Run parameters:

set pop 5000 200 20

% --- Geometry plot:

plot 1 500 500  10
plot 1 500 500 -10

% --- Mesh plots:

mesh 10 1 500 500
mesh 1 500 500

% --- Power level:

set power 8.0

./constant/polyMesh/points-file

"./constant/polyMesh/points" follows the unstructured mesh points file-format. 

27
(1 -1 -1)
(1 0 1)
(0 0 -1)
(0 1 1)
(1 1 0)
(1 0 0)
(0 0 0)
(0 1 0)
(1 1 -1)
(1 0 -1)
(0 0 1)
(0 1 -1)
(1 -1 1)
(0 -1 1)
(1 -1 0)
(0 -1 0)
(1 1 1)
(0 -1 -1)
(-1 1 1)
(-1 0 1)
(-1 1 0)
(-1 0 0)
(-1 1 -1)
(-1 0 -1)
(-1 -1 1)
(-1 -1 0)
(-1 -1 -1)

./constant/polyMesh/faces-file

"./constant/polyMesh/faces" follows the unstructured mesh faces file-format. 

36
4(5 6 7 4)
4(14 15 6 5)
4(15 25 21 6)
4(6 21 20 7)
4(7 6 10 3)
4(15 13 10 6)
4(17 15 6 2)
4(2 6 7 11)
4(5 1 10 6)
4(9 5 6 2)
4(23 2 6 21)
4(6 10 19 21)
4(3 10 1 16)
4(13 12 1 10)
4(24 13 10 19)
4(19 10 3 18)
4(8 9 2 11)
4(9 0 17 2)
4(2 17 26 23)
4(11 2 23 22)
4(1 5 4 16)
4(5 9 8 4)
4(5 14 0 9)
4(1 12 14 5)
4(21 19 18 20)
4(25 24 19 21)
4(26 25 21 23)
4(23 21 20 22)
4(4 7 3 16)
4(7 20 18 3)
4(11 22 20 7)
4(8 11 7 4)
4(13 15 14 12)
4(15 17 0 14)
4(25 26 17 15)
4(24 25 15 13)


./constant/polyMesh/owner-file

"./constant/polyMesh/owner" follows the unstructured mesh owner file-format. 

36
0
1
5
4
0
1
3
2
0
2
6
4
0
1
5
4
2
3
7
6
0
2
3
1
4
5
7
6
0
4
6
2
1
3
7
5

./constant/polyMesh/neighbour-file

"./constant/polyMesh/neighbour" follows the unstructured mesh neighbour file-format. Only the 12 first faces have a neighbouring cell. 


12
2
3
7
6
4
5
7
6
1
3
7
5

./constant/polyMesh/materials-file

"./constant/polyMesh/materials" follows the unstructured mesh material file-format. 


8
fuelHiU
fuelHiU
fuelLoU
fuelLoU
fuelHiU
fuelHiU
fuelLoU
fuelLoU

Traditional geometry + unstructured mesh based interface

The number of separate material definitions that are needed can be reduced to two by bringing in the temperature and density data via the multi-physics interface. The two nuclide compositions still have to be separated into their own materials. This input creates the geometry by splitting the inner region into eight sub-regions using the coordinate planes. The correct material is then filled into each octant. The temperature and density data are specified in the material card.

Main input file

set title "8 cubes hexahedron test"

% --- Boundary of geometry:

surf 2  cuboid -150 150 -150 150 -150 150

% --- Boundary at infinity

surf 3 inf

% --- yz-plane (not needed)

%surf yzPlane px 0.0

% --- xz-plane (not needed)

%surf xzPlane py 0.0

% --- xy-plane

surf xyPlane pz 0.0

% --- Cube with two metre edge length:

surf 2metreCube cuboid -100 100 -100 100 -100 100

% --- Geometry based on the normal CSG-model

cell HiHiHi 0    fuelHiU    xyPlane -2metreCube
cell HiLoHi 0    fuelLoU   -xyPlane -2metreCube

% --- Blanket cell around the eight cubes

cell 11  0 blanket   2metreCube -2

% --- Outside the geometry

cell 20  0 outside    2

% --- Black BC

set bc 1

% --- Temperature and density information from interface

ifc "./type8.ifc"

% --- Fuel salts:

% --- Material for cubes at (?,?,+)
mat fuelHiU     -4.10 
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65         
U-233.06c        2.85

% --- Material for cubes at (?,?,-)
mat fuelLoU     -4.10 
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65         
U-233.06c        1.425

% --- Blanket material 
mat blanket     -0.10
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65         
U-233.06c        2.85

% --- Run parameters:

set pop 5000 200 20

% --- Geometry plot:

plot 1 500 500 10
plot 1 500 500 -10

% --- Mesh plots:

mesh 10 1 500 500
mesh 1 500 500

% --- Power level:

set power 8.0

./type8.ifc file

Here the interface file "./type8.ifc" has been linked to the main input file. The contents of this interface file using the type 8 interface format are presented here: 

8 fuelHiU 1
./0/volpower
-1 600
5 3 2 2 2
./constant/polyMesh/points
./constant/polyMesh/faces
./constant/polyMesh/owner
./constant/polyMesh/neighbour
./constant/polyMesh/materials
./0/rho 1  
./0/T 1   
./constant/polyMesh/map

./constant/polyMesh/points file

"./constant/polyMesh/points" follows the unstructured mesh points file-format. 

27
(1 -1 -1)
(1 0 1)
(0 0 -1)
(0 1 1)
(1 1 0)
(1 0 0)
(0 0 0)
(0 1 0)
(1 1 -1)
(1 0 -1)
(0 0 1)
(0 1 -1)
(1 -1 1)
(0 -1 1)
(1 -1 0)
(0 -1 0)
(1 1 1)
(0 -1 -1)
(-1 1 1)
(-1 0 1)
(-1 1 0)
(-1 0 0)
(-1 1 -1)
(-1 0 -1)
(-1 -1 1)
(-1 -1 0)
(-1 -1 -1)

./constant/polyMesh/faces file

"./constant/polyMesh/faces" follows the unstructured mesh faces file-format. 

36
4(5 6 7 4)
4(14 15 6 5)
4(15 25 21 6)
4(6 21 20 7)
4(7 6 10 3)
4(15 13 10 6)
4(17 15 6 2)
4(2 6 7 11)
4(5 1 10 6)
4(9 5 6 2)
4(23 2 6 21)
4(6 10 19 21)
4(3 10 1 16)
4(13 12 1 10)
4(24 13 10 19)
4(19 10 3 18)
4(8 9 2 11)
4(9 0 17 2)
4(2 17 26 23)
4(11 2 23 22)
4(1 5 4 16)
4(5 9 8 4)
4(5 14 0 9)
4(1 12 14 5)
4(21 19 18 20)
4(25 24 19 21)
4(26 25 21 23)
4(23 21 20 22)
4(4 7 3 16)
4(7 20 18 3)
4(11 22 20 7)
4(8 11 7 4)
4(13 15 14 12)
4(15 17 0 14)
4(25 26 17 15)
4(24 25 15 13)


./constant/polyMesh/owner file

"./constant/polyMesh/owner" follows the unstructured mesh owner file-format. 

36
0
1
5
4
0
1
3
2
0
2
6
4
0
1
5
4
2
3
7
6
0
2
3
1
4
5
7
6
0
4
6
2
1
3
7
5

./constant/polyMesh/neighbour file

"./constant/polyMesh/neighbour" follows the unstructured mesh neighbour file-format. Only the 12 first faces have a neighbouring cell. 


12
2
3
7
6
4
5
7
6
1
3
7
5

./constant/polyMesh/materials file

"./constant/polyMesh/materials" follows the unstructured mesh material file-format. 

8
fuelHiU
fuelHiU
fuelLoU
fuelLoU
fuelHiU
fuelHiU
fuelLoU
fuelLoU

./0/rho file

"./0/rho" follows the unstructured mesh density file-format. 

8
4.1
4.1
4.1
4.1
2.05
2.05
2.05
2.05


./0/T file

"./0/T" follows the unstructured mesh temperature file-format. 

8
1200
600
1200
600
1200
600
1200
600

Unstructured mesh based geometry and interface

In this input file both the geometry (material information) and the temperature and density information are brought in using the solid 3 input card, which uses the type 9 multi-physics interface format.

This is the suggested way to define the material, temperature and density distributions if the geometry is to be created based on the unstructured mesh and temperature and density data is to be brought in using the same unstructured mesh. If no temperature and density distributions are needed the geometry can be created separately using the solid 1 input card. If the geometry can be created using the normal CSG definitions the temperature and density fields can be brought in using the type 7 or type 8 multi-physics interface format.

Main input file

set title "8 cubes hexahedron test, solid 3"

% --- Boundary of geometry:

surf 2  cuboid -150 150 -150 150 -150 150

% --- Boundary at infinity

surf 3 inf

% --- OpenFOAM mesh based geometry (universe 1, bg universe 2)
%     Search mesh split condition is 5 cells
%     Search mesh has maximum of two levels with maximum of 2^n 
%     cells per level

solid 3
"./type9.ifc"

% --- Blanket cell in universe 2 (background universe)

cell 11  2 blanket   -3

% --- Geometry consists of mesh-based universe and background universe

cell 19  0 fill 1    -2

% --- Outside the geometry

cell 20  0 outside    2

% --- Black BC

set bc 1

% --- Fuel salts:
% --- Material for cubes at (?,?,+)
mat fuelHiU     -4.10
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65
U-233.06c        2.85

% --- Material for cubes at (?,?,-)
mat fuelLoU     -4.10
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65
U-233.06c        1.425

% --- Blanket material
mat blanket     -0.10
Li-7.06c        77.50
F-19.06c       167.50
Th-232.06c      19.65
U-233.06c        2.85

% --- Run parameters:

set pop 5000 200 20

% --- Geometry plot:

plot 1 500 500  10
plot 1 500 500 -10

% --- Power level:

set power 8.0

./type9.ifc file

The contents of the interface file follow the type 9 multi-physics interface format: 

9 1 2
1 ./volpower
-1 600
5 3 2 2 2
./constant/polyMesh/points
./constant/polyMesh/faces
./constant/polyMesh/owner
./constant/polyMesh/neighbour
./constant/polyMesh/materials
./0/rho 1  
./0/T 1   
./constant/polyMesh/map
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