Design error in reactor nuclear simulation in serpent code

AI Thread Summary
Errors in the geometry of the VVER-1200 core design in the Serpent nuclear code are primarily related to cell definitions and lost particles. The discussion highlights the absence of material definitions, which are necessary for proper simulation, as materials like fuel, clad, and water need to be specified using "mat" cards. Users are encouraged to refer to the Serpent webpage for examples of correct material definitions. Addressing these issues is crucial for resolving the geometry errors encountered. Properly defining materials will enhance the accuracy and functionality of the simulation.
emilmammadzada
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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]
 
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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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