Difference between revisions of "Tutorial"
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=== Basics === | === Basics === | ||
| + | |||
| + | <div class="toccolours mw-collapsible mw-collapsed" style="width:60em;"> | ||
| + | '''Input for 2D pin-cell geometry''' | ||
| + | <div class="mw-collapsible-content"> | ||
| + | <nowiki>% --- Simple 2D PWR pin-cell geometry for Serpent tutorial | ||
| + | |||
| + | /************************ | ||
| + | * Material definitions * | ||
| + | ************************/ | ||
| + | |||
| + | % --- Fuel material (3.0 wt-% enriched uranium dioxide), density 10.1 g/cm3 | ||
| + | |||
| + | mat fuel -10.1 | ||
| + | 92235.03c -0.02644492 | ||
| + | 92238.03c -0.85505247 | ||
| + | 8016.03c -0.11850261 | ||
| + | |||
| + | % --- Cladding material for fuel rod | ||
| + | % (100 % Zirconium) | ||
| + | |||
| + | mat clad -6.55 | ||
| + | 40000.03c -1.0 | ||
| + | |||
| + | % --- Water at 1.0 g/cm3 | ||
| + | |||
| + | mat water -1.0 | ||
| + | 1001.03c 2.0 | ||
| + | 8016.03c 1.0 | ||
| + | |||
| + | /************************ | ||
| + | * Geometry definitions * | ||
| + | ************************/ | ||
| + | |||
| + | % --- Fuel pin structure | ||
| + | |||
| + | pin p1 | ||
| + | fuel 0.4025 | ||
| + | clad 0.4750 | ||
| + | water | ||
| + | |||
| + | % --- Square surface with 1.0 cm side centered at (x,y) = (0,0) | ||
| + | |||
| + | surf s1 sqc 0.0 0.0 0.5 | ||
| + | |||
| + | cell c1 0 fill p1 -s1 | ||
| + | cell c2 0 outside s1 | ||
| + | |||
| + | /****************** | ||
| + | * Run parameters * | ||
| + | ******************/ | ||
| + | |||
| + | % --- Neutron population | ||
| + | |||
| + | set pop 5000 100 20 | ||
| + | |||
| + | % --- Boundary condition (1 = black, 2 = reflective, 3 = periodic) | ||
| + | |||
| + | set bc 2 | ||
| + | |||
| + | % --- Geometry plots | ||
| + | |||
| + | plot 3 200 200 | ||
| + | plot 3 1000 1000 0.0 -2.5 2.5 -2.5 2.5 | ||
| + | |||
| + | % --- Cross section library file | ||
| + | |||
| + | set acelib "xsdir0K"</nowiki> | ||
| + | </div> | ||
| + | </div> | ||
=== Testing and tinkering === | === Testing and tinkering === | ||
Revision as of 13:46, 8 September 2017
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.
Contents
Pre-requisite
Compiled version of Serpent 2
Basics of Serpent input
Explain different (typical) parts such as:
- Material definitions
- Geometry definitions
- Run parameters/options
2D Pin-cell model
Overview
Basics
Input for 2D pin-cell geometry
% --- Simple 2D PWR pin-cell geometry for Serpent tutorial /************************ * Material definitions * ************************/ % --- Fuel material (3.0 wt-% enriched uranium dioxide), density 10.1 g/cm3 mat fuel -10.1 92235.03c -0.02644492 92238.03c -0.85505247 8016.03c -0.11850261 % --- Cladding material for fuel rod % (100 % Zirconium) mat clad -6.55 40000.03c -1.0 % --- Water at 1.0 g/cm3 mat water -1.0 1001.03c 2.0 8016.03c 1.0 /************************ * Geometry definitions * ************************/ % --- Fuel pin structure pin p1 fuel 0.4025 clad 0.4750 water % --- Square surface with 1.0 cm side centered at (x,y) = (0,0) surf s1 sqc 0.0 0.0 0.5 cell c1 0 fill p1 -s1 cell c2 0 outside s1 /****************** * Run parameters * ******************/ % --- Neutron population set pop 5000 100 20 % --- Boundary condition (1 = black, 2 = reflective, 3 = periodic) set bc 2 % --- Geometry plots plot 3 200 200 plot 3 1000 1000 0.0 -2.5 2.5 -2.5 2.5 % --- Cross section library file set acelib "xsdir0K"
