Difference between revisions of "Tutorial"

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

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)

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
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"
```