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

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

% --- Cross section library file

set acelib "xsdir0K"