Design error in reactor nuclear simulation in serpent code

In summary, the article discusses a design error identified in the Serpent code, used for nuclear reactor simulations. This error impacts the accuracy of modeling reactor behavior, potentially leading to miscalculations in safety assessments and operational predictions. The authors highlight the importance of rigorous validation and verification processes in computational tools to prevent such issues, emphasizing the need for continuous improvement in simulation software to ensure reliability in nuclear engineering applications.
  • #1
emilmammadzada
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TL;DR Summary
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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  • #2
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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