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
