The printable version is no longer supported and may have rendering errors. Please update your browser bookmarks and please use the default browser print function instead.
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 model
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: 5000 neutrons per cycle, 100 active / 20 inactive cycles
set pop 5000 100 20
Testing and tinkering
2D Pin-cell model
Overview
Basics
Colors in input correspond to:
- Comments
- Control words
- Name definitions
- Name references
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 belongs to the base universe 0, is filled with the pin p1
% and covers everything inside surface s1
cell c1 0 fill p1 -s1
% --- Cell c2 belongs to the base universe 0, is defined as an "outside" cell
% and covers everything inside surface 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
Testing and tinkering
2D Assembly model
Overview
Basics
Testing and tinkering