Design error in reactor nuclear simulation in serpent code

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SUMMARY

The discussion centers on resolving geometry errors encountered while designing a VVER-1200 core using the Serpent code. The user reports issues with cell definitions and lost particles, indicating a need for proper material definitions. The community emphasizes the necessity of using "mat" cards to define materials such as fuel, clad, and water, which are crucial for accurate simulations in Serpent 2.1.30.

PREREQUISITES
  • Understanding of Serpent 2.1.30 simulation code
  • Knowledge of VVER-1200 reactor design principles
  • Familiarity with geometry definitions in nuclear simulations
  • Experience with material definitions using "mat" cards
NEXT STEPS
  • Review the Serpent documentation on material definitions and "mat" cards
  • Study examples of VVER-1200 core designs implemented in Serpent
  • Learn about debugging geometry errors in Serpent simulations
  • Explore best practices for defining cell and surface parameters in nuclear reactor models
USEFUL FOR

Nuclear engineers, reactor designers, and researchers working with the Serpent code who are focused on simulating VVER-1200 reactor geometries and resolving related errors.

emilmammadzada
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TL;DR
Design error in reactor nuclear simulation in serpent code
Dear experts, I would like to get help from you on something. I want to design a vver -1200 core in the serpent nuclear code, but I am getting errors in the geometry I defined below. I would like to get help from you on how to fix these errors.I seem to be getting errors in cell definitions and it is related to the lost particle. I would be very happy if you could help me with this.
Code:
[
% --- Fuel pin with central hole:

pin 1
helium   0.08000
fuel   0.38000
helium   0.38650
clad   0.45500
water   

% --- Fuel pin2 with central hole:

pin 5
helium   0.08000
fuel1   0.38000
helium   0.38650
clad   0.45500
water   

% --- Central tube:

pin 2 
water  0.05450
clad   0.06000
water 

% --- Guide tube:

pin 4 
water  0.38000
clad   0.45500
water   

% --- Empty lattice position:

pin 3
water 

% --- Empty lattice position:

pin 7
water   

% --- Assembly Lattice (type = 2, pin pitch = 1.2750 cm):

lat 10  3  0.0 0.0 23 23 1.2750
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
 3 3 3 3 3 3 3 3 3 3 3 1 1 1 1 1 1 1 1 1 1 1 3
  3 3 3 3 3 3 3 3 3 3 1 1 1 1 1 1 1 1 1 1 1 1 3  
   3 3 3 3 3 3 3 3 3 1 1 1 1 1 1 1 1 1 1 1 1 1 3 
    3 3 3 3 3 3 3 3 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 
     3 3 3 3 3 3 3 1 1 1 1 1 1 1 4 1 1 1 1 1 1 1 3
      3 3 3 3 3 3 1 1 1 1 1 4 5 5 5 5 4 1 1 1 1 1 3
       3 3 3 3 3 1 1 1 1 1 5 5 5 5 5 5 5 1 1 1 1 1 3
        3 3 3 3 1 1 1 1 4 5 5 5 4 5 5 5 5 4 1 1 1 1 3
         3 3 3 1 1 1 1 1 5 5 5 5 5 5 4 5 5 1 1 1 1 1 3 
          3 3 1 1 1 1 1 5 5 4 5 5 5 5 5 5 5 1 1 1 1 1 3
           3 1 1 1 1 1 4 5 5 5 5 2 5 5 5 5 4 1 1 1 1 1 3
            3 1 1 1 1 1 5 5 5 5 5 5 5 4 5 5 1 1 1 1 1 3 3
             3 1 1 1 1 1 5 5 4 5 5 5 5 5 5 1 1 1 1 1 3 3 3 
              3 1 1 1 1 4 5 5 5 5 4 5 5 5 4 1 1 1 1 3 3 3 3
               3 1 1 1 1 1 5 5 5 5 5 5 5 1 1 1 1 1 3 3 3 3 3
                3 1 1 1 1 1 4 5 5 5 5 4 1 1 1 1 1 3 3 3 3 3 3
                 3 1 1 1 1 1 1 1 4 1 1 1 1 1 1 1 3 3 3 3 3 3 3
                  3 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 3 3 3 3 3 3 3
                   3 1 1 1 1 1 1 1 1 1 1 1 1 1 3 3 3 3 3 3 3 3 3
                    3 1 1 1 1 1 1 1 1 1 1 1 1 3 3 3 3 3 3 3 3 3 3 
                     3 1 1 1 1 1 1 1 1 1 1 1 3 3 3 3 3 3 3 3 3 3 3
                      3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 

% --- Surfaces (assembly pitch = 22.7 cm):

surf 1  hexyprism    0.0  0.0  11.555 0.0 10 % Shroud tube inner radius
surf 2  hexyprism    0.0  0.0  11.650 0.0 10 % Shroud tube outer radius
surf 3  hexyprism    0.0  0.0  11.750 0.0 10  % Outer boundary

% --- Cells:

cell  1  6  fill 10  -1        % Pin lattice                 
cell  4  6  tube      1    -2  % Shroud tube                
cell  5  6  water     2    -3  % Water in channel                
cell 99  0  outside         3  % Outside world                

% --- Core Lattice (type = 2, pin pitch = 22.7 cm):

lat 100  2  0.0 0.0 17 17 22.7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
 7 7 7 7 7 7 7 7 6 6 6 6 6 6 6 6 7
  7 7 7 7 7 7 7 6 6 6 6 6 6 6 6 6 7
   7 7 7 7 7 7 6 6 6 6 6 6 6 6 6 6 7
    7 7 7 7 7 6 6 6 6 6 6 6 6 6 6 6 7
     7 7 7 7 6 6 6 6 6 6 6 6 6 6 6 6 7
      7 7 7 6 6 6 6 6 6 6 6 6 6 6 6 6 7
       7 7 6 6 6 6 6 6 6 6 6 6 6 6 6 6 7
        7 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 7
         7 6 6 6 6 6 6 6 6 6 6 6 6 6 6 7 7
          7 6 6 6 6 6 6 6 6 6 6 6 6 6 7 7 7
           7 6 6 6 6 6 6 6 6 6 6 6 6 7 7 7 7
            7 6 6 6 6 6 6 6 6 6 6 6 7 7 7 7 7
             7 6 6 6 6 6 6 6 6 6 6 7 7 7 7 7 7
              7 6 6 6 6 6 6 6 6 6 3 7 7 7 7 7 7
               7 6 6 6 6 6 6 6 6 7 7 7 7 7 7 7 7
                7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
 

% --- Surfaces (assembly pitch = 340cm):
%-----Outer VVER
% --- Surfaces (core pitch = 340 cm):

%surf 10  hexyc    0.0  0.0  170.05  % Shroud tube inner radius
%surf 20  hexyc    0.0  0.0  170.15  % Shroud tube outer radius
%surf 30  hexyc    0.0  0.0  170.25  % Outer boundary
surf 50  cyl 0.0 0.0 173.16890 0.0 10 % Pressure tube inner wall
surf 60  cyl 0.0 0.0 173.60320 0.0 10 % Pressure tube outer wall
surf 90  sqc 0.0 0.0 190.09570   % Outer boundary
% --- Cells:

cell 300  300  fill 100 -50      % Pin lattice
cell 400  0  tube      50  -60 % Pressure tube
cell 500  0  water     60  -90  % Void between tubes
cell 600  0  outside   90     % Outside world]
 
Last edited by a moderator:
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I removed the beginning and ending brackets.

Next, I don't see any materials defined in your input. You should use "mat" cards to define fuel, fuel1, clad, helium, water, etc. Look on the Serpent webpage for examples.
 
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