Difference between revisions of "Tutorial"

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(Basics of Serpent input)
(Basics)
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=== Basics ===
 
=== Basics ===
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<div class="toccolours mw-collapsible mw-collapsed" style="width:60em;">
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'''Input for 2D pin-cell geometry'''
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<div class="mw-collapsible-content">
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<nowiki>% --- Simple 2D PWR pin-cell geometry for Serpent tutorial
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/************************
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* Material definitions *
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************************/
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% --- Fuel material (3.0 wt-% enriched uranium dioxide), density 10.1 g/cm3
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mat fuel    -10.1
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92235.03c    -0.02644492
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92238.03c    -0.85505247
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8016.03c    -0.11850261
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% --- Cladding material for fuel rod
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%    (100 % Zirconium)
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mat clad    -6.55
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40000.03c    -1.0
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% --- Water at 1.0 g/cm3
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mat water    -1.0
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1001.03c    2.0
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8016.03c    1.0
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/************************
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* Geometry definitions *
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************************/
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% --- Fuel pin structure
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pin p1
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fuel    0.4025
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clad    0.4750
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water
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% --- Square surface with 1.0 cm side centered at (x,y) = (0,0)
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surf s1 sqc 0.0 0.0 0.5
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cell c1 0 fill p1  -s1
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cell c2 0 outside    s1
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/******************
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* Run parameters *
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******************/
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% --- Neutron population
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set pop 5000 100 20
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% --- Boundary condition (1 = black, 2 = reflective, 3 = periodic)
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set bc 2
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% --- Geometry plots
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plot 3  200  200
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plot 3 1000 1000 0.0 -2.5 2.5 -2.5 2.5
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% --- Cross section library file
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set acelib "xsdir0K"</nowiki>
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</div>
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</div>
  
 
=== Testing and tinkering ===
 
=== Testing and tinkering ===

Revision as of 13:46, 8 September 2017

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

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 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"

Testing and tinkering

2D Assembly model

Overview

Basics

Testing and tinkering