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| *Run parameters/options | | *Run parameters/options |
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| == 2D Pin-cell model == | | == Infinite homogeneous system == |
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| === Overview === | | === Overview === |
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| '''Input for 2D pin-cell geometry''' | | '''Input for 2D pin-cell geometry''' |
| <div class="mw-collapsible-content"> | | <div class="mw-collapsible-content"> |
| <span style="color: Green;">% --- Simple 2D PWR pin-cell geometry for Serpent tutorial | | <span style="color: Green;">% --- Very simple infinite homogeneous geometry for Serpent tutorial |
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| /************************ | | /************************ |
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| ************************/ | | ************************/ |
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| % --- Fuel material (3.0 wt-% enriched uranium dioxide), density 10.1 g/cm3</span> | | % --- Fuel material (4.0 wt-% enriched uranium dioxide), density 10.1 g/cm3</span> |
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| <span style="color: Red;">mat</span> <span style="color: Blue;">fuel</span> -10.1 | | mat fuel -10.1 |
| 92235.03c -0.02644492 | | 92235.03c -0.04 |
| 92238.03c -0.85505247 | | 92238.03c -0.96 |
| 8016.03c -0.11850261
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| <span style="color: Green;">% --- Cladding material for fuel rod | | /************************ |
| % (100 % Zirconium)</span>
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| <span style="color: Red;">mat</span> <span style="color: Blue;">clad</span> -6.55
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| 40000.03c -1.0
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| <span style="color: Green;">% --- Water at 1.0 g/cm3</span>
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| <span style="color: Red;">mat</span> <span style="color: Blue;">water</span> -1.0
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| 1001.03c 2.0
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| 8016.03c 1.0
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| <span style="color: Green;">/************************
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| * Geometry definitions * | | * Geometry definitions * |
| ************************/</span> | | ************************/ |
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| <span style="color: Green;">% --- Fuel pin structure</span>
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| <span style="color: Red;">pin</span> <span style="color: Blue;">p1</span> | | % --- "Surface" at infinity |
| <span style="color: Purple;">fuel</span> 0.4025
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| <span style="color: Purple;">clad</span> 0.4750
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| <span style="color: Purple;">water</span>
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| <span style="color: Green;">% --- Square surface with 1.0 cm side centered at (x,y) = (0,0)</span> | | surf s1 inf |
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| <span style="color: Red;">surf</span> <span style="color: Blue;">s1</span> sqc 0.0 0.0 0.5 | | % --- Cell c1 belongs to the base universe 0, contains the material fuel |
| | % and covers everything inside surface s1 |
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| <span style="color: Green;">% --- Cell c1 belongs to the base universe 0, is filled with the pin p1 | | cell c1 0 fuel -s1 |
| % and covers everything inside surface s1</span>
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| <span style="color: Red;">cell</span> <span style="color: Blue;">c1</span> 0 fill <span style="color: Purple;">p1</span> -<span style="color: Purple;">s1</span> | | % --- Cell c2 belongs to the base universe 0, is defined as an "outside" cell |
| | % and covers everything outside surface s1 |
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| <span style="color: Green;">% --- Cell c2 belongs to the base universe 0, is defined as an "outside" cell | | cell c2 0 outside s1 |
| % and covers everything inside surface s1</span>
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| <span style="color: Red;">cell</span> <span style="color: Blue;">c2</span> 0 outside <span style="color: Purple;">s1</span> | | /****************** |
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| <span style="color: Green;">/******************
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| * Run parameters * | | * Run parameters * |
| ******************/</span> | | ******************/ |
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| <span style="color: Green;">% --- Neutron population</span>
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| <span style="color: Red;">set pop</span> 5000 100 20
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| <span style="color: Green;">% --- Boundary condition (1 = black, 2 = reflective, 3 = periodic)</span>
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| <span style="color: Red;">set bc</span> 2
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| <span style="color: Green;">% --- Geometry plots</span> | | % --- Neutron population |
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| <span style="color: Red;">plot</span> 3 200 200 | | set pop 5000 100 20 |
| <span style="color: Red;">plot</span> 3 1000 1000 0.0 -2.5 2.5 -2.5 2.5
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| </div> | | </div> |
| </div> | | </div> |
This page is the beginning of a hands-on tutorial in Serpent that will walk you through the creation of simple pin-cell and assembly geometry models and the use of those models for some reactor physics simulations.
Pre-requisite
Compiled version of Serpent 2
Basics of Serpent input
Explain different (typical) parts such as:
- Material definitions
- Geometry definitions
- Run parameters/options
Infinite homogeneous system
Overview
Basics
Colors in input correspond to:
- Comments
- Control words
- Name definitions
- Name references
Input for 2D pin-cell geometry
% --- Very simple infinite homogeneous geometry for Serpent tutorial
/************************
* Material definitions *
************************/
% --- Fuel material (4.0 wt-% enriched uranium dioxide), density 10.1 g/cm3
mat fuel -10.1
92235.03c -0.04
92238.03c -0.96
/************************
* Geometry definitions *
************************/
% --- "Surface" at infinity
surf s1 inf
% --- Cell c1 belongs to the base universe 0, contains the material fuel
% and covers everything inside surface s1
cell c1 0 fuel -s1
% --- Cell c2 belongs to the base universe 0, is defined as an "outside" cell
% and covers everything outside surface s1
cell c2 0 outside s1
/******************
* Run parameters *
******************/
% --- Neutron population
set pop 5000 100 20
Testing and tinkering
2D Assembly model
Overview
Basics
Testing and tinkering