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
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
