Simple umsh 8 cubes input
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 density (different nuclide density for macroscopic cross sections).
- Areas with positive y (?,+,?) have a larger temperature (different temperature for cross sections).
- Areas with positive z (?,?,+) have a larger U-233 content (different material composition).
In the following sections this geometry is created in several different ways:
- Using the normal Serpent geometry definitions with separate materials for all 8 regions.
- Using the unstructured mesh based geometry definition with separate materials for all 8 regions.
- Using the normal Serpent geometry definitions with temperature and density data brought in using the unstructured mesh based interface.
- 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.
set title "8 cubes hexahedron test, CSG geo" include "/home/vvvillehe/Serpent2/serpdefaults.txt" % --- 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
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.
set title "8 cubes hexahedron test, CSG geo" include "/home/vvvillehe/Serpent2/serpdefaults.txt" % --- 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