Difference between revisions of "Tutorial"

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*Run parameters/options
 
*Run parameters/options
  
−
== 2D Pin-cell model ==
+
== Infinite homogeneous system ==
  
 
=== Overview ===
 
=== Overview ===
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'''Input for 2D pin-cell geometry'''
 
'''Input for 2D pin-cell geometry'''
 
<div class="mw-collapsible-content">
 
<div class="mw-collapsible-content">
−
  <span style="color: Green;">% --- Simple 2D PWR pin-cell geometry for Serpent tutorial
+
  <span style="color: Green;">% --- Very simple infinite homogeneous geometry for Serpent tutorial
 
   
 
   
 
  /************************
 
  /************************
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   ************************/
 
   ************************/
 
   
 
   
−
  % --- Fuel material (3.0 wt-% enriched uranium dioxide), density 10.1 g/cm3</span>
+
  % --- Fuel material (4.0 wt-% enriched uranium dioxide), density 10.1 g/cm3</span>
 
   
 
   
−
  <span style="color: Red;">mat</span> <span style="color: Blue;">fuel</span>     -10.1
+
  mat fuel    -10.1
−
  92235.03c    -0.02644492
+
  92235.03c    -0.04
−
  92238.03c    -0.85505247
+
  92238.03c    -0.96
−
  8016.03c    -0.11850261
 
 
   
 
   
−
  <span style="color: Green;">% --- Cladding material for fuel rod
+
  /************************
−
%    (100 % Zirconium)</span>
 
−
 
−
<span style="color: Red;">mat</span> <span style="color: Blue;">clad</span>    -6.55
 
−
40000.03c    -1.0
 
−
 
−
<span style="color: Green;">% --- Water at 1.0 g/cm3</span>
 
−
 
−
<span style="color: Red;">mat</span> <span style="color: Blue;">water</span>    -1.0
 
−
  1001.03c    2.0
 
−
  8016.03c    1.0
 
−
 
−
<span style="color: Green;">/************************
 
 
   * Geometry definitions *
 
   * Geometry definitions *
−
   ************************/</span>
+
   ************************/
−
 
−
<span style="color: Green;">% --- Fuel pin structure</span>
 
 
   
 
   
−
  <span style="color: Red;">pin</span> <span style="color: Blue;">p1</span>
+
  % --- "Surface" at infinity
−
<span style="color: Purple;">fuel</span>    0.4025
 
−
<span style="color: Purple;">clad</span>    0.4750
 
−
<span style="color: Purple;">water</span>
 
 
   
 
   
−
  <span style="color: Green;">% --- Square surface with 1.0 cm side centered at (x,y) = (0,0)</span>
+
  surf s1 inf
 
   
 
   
−
  <span style="color: Red;">surf</span> <span style="color: Blue;">s1</span> sqc 0.0 0.0 0.5
+
  % --- Cell c1 belongs to the base universe 0, contains the material fuel
 +
%    and covers everything inside surface s1
 
   
 
   
−
  <span style="color: Green;">% --- Cell c1 belongs to the base universe 0, is filled with the pin p1
+
  cell c1 0 fuel      -s1
−
%    and covers everything inside surface s1</span>
 
 
   
 
   
−
  <span style="color: Red;">cell</span> <span style="color: Blue;">c1</span> 0 fill <span style="color: Purple;">p1</span>  -<span style="color: Purple;">s1</span>
+
  % --- Cell c2 belongs to the base universe 0, is defined as an "outside" cell
 +
%    and covers everything outside surface s1
 
   
 
   
−
  <span style="color: Green;">% --- Cell c2 belongs to the base universe 0, is defined as an "outside" cell
+
  cell c2 0 outside   s1
−
%    and covers everything inside surface s1</span>
 
 
   
 
   
−
  <span style="color: Red;">cell</span> <span style="color: Blue;">c2</span> 0 outside    <span style="color: Purple;">s1</span>
+
  /******************
−
 
−
<span style="color: Green;">/******************
 
 
   * Run parameters *
 
   * Run parameters *
−
   ******************/</span>
+
   ******************/
−
 
−
<span style="color: Green;">% --- Neutron population</span>
 
−
 
−
<span style="color: Red;">set pop</span> 5000 100 20
 
−
 
−
<span style="color: Green;">% --- Boundary condition (1 = black, 2 = reflective, 3 = periodic)</span>
 
−
 
−
<span style="color: Red;">set bc</span> 2
 
 
   
 
   
−
  <span style="color: Green;">% --- Geometry plots</span>
+
  % --- Neutron population
 
   
 
   
−
  <span style="color: Red;">plot</span> 3  200  200
+
  set pop 5000 100 20
−
<span style="color: Red;">plot</span> 3 1000 1000 0.0 -2.5 2.5 -2.5 2.5
 
 
</div>
 
</div>
 
</div>
 
</div>

Revision as of 10:31, 11 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

Infinite homogeneous system

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

set pop 5000 100 20

Testing and tinkering

2D Assembly model

Overview

Basics

Testing and tinkering

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