2D VVER-440 fuel assembly geometry

% --- VVER-440 Assembly --------------------------------------

set title "VVER-440"

% --- Fuel pin with central hole:

pin 1
void   0.07000
fuel   0.38000
void   0.39000
clad   0.45500
water   

% --- Central tube:

pin 2 
water  0.44000
clad   0.51500
water   

% --- Empty lattice position:

pin 3
water   

% --- Lattice (type = 2, pin pitch = 1.23 cm):

lat 10  2  0.0 0.0 15 15 1.23
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 3
  3 3 3 3 3 3 1 1 1 1 1 1 1 1 3 
   3 3 3 3 3 1 1 1 1 1 1 1 1 1 3 
    3 3 3 3 1 1 1 1 1 1 1 1 1 1 3 
     3 3 3 1 1 1 1 1 1 1 1 1 1 1 3
      3 3 1 1 1 1 1 1 1 1 1 1 1 1 3
       3 1 1 1 1 1 1 2 1 1 1 1 1 1 3
        3 1 1 1 1 1 1 1 1 1 1 1 1 3 3
         3 1 1 1 1 1 1 1 1 1 1 1 3 3 3 
          3 1 1 1 1 1 1 1 1 1 1 3 3 3 3
           3 1 1 1 1 1 1 1 1 1 3 3 3 3 3
            3 1 1 1 1 1 1 1 1 3 3 3 3 3 3
             3 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 

% --- Surfaces (assembly pitch = 14.7 cm):

surf 1  hexyc    0.0  0.0  7.100  % Shroud tube inner radius
surf 2  hexyc    0.0  0.0  7.250  % Shroud tube outer radius
surf 3  hexyc    0.0  0.0  7.350  % Outer boundary

% --- Cells:

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

% --- UO2 fuel enriched to 3.6 wt-% U-235:

mat fuel   -10.45000
92235.09c   -0.03173
92238.09c   -0.84977
 8016.09c   -0.11850

% --- Zr-Nb cladding and shroud tube:

mat clad    -6.55000
40000.06c   -0.99000
41093.06c   -0.01000

mat tube    -6.55000
40000.06c   -0.97500
41093.06c   -0.02500

% --- Water: (1 ppm boron for iteration)

mat water   -0.7207  moder lwtr 1001
 1001.06c    2.0
 8016.06c    1.0
 5010.06c    0.2E-6
 5011.06c    0.8E-6

% --- Iterate critical boron concentration:

set iter nuc 50 1.0 2 50100 50110 1 water

% --- Thermal scattering data for light water:

therm lwtr lwj3.11t

% --- Cross section library file path:

set acelib "sss_jeff31u.xsdata"

% --- Periodic boundary condition:

set bc 3

% --- Neutron population and criticality cycles:

set pop 2000 500 20

% --- Mesh plot:

mesh 3 500 500

% --- Geometry plots:

plot 30 500 500  % No boundaries
plot 31 500 500  % Cell boundaries
plot 32 500 500  % Material boundaries (default)
plot 33 500 500  % Both cell amd material boundaries

% --- Detector energy grid (uniform lethargy):

ene 1 3 1000 1E-9 12.0

% --- Flux per lethargy:

det 1 de 1 dt -3

% --- Differential capture, fission and production spectra:

det 2 de 1 dt -2 dr -2 void
det 3 de 1 dt -2 dr -6 void
det 4 de 1 dt -2 dr -7 void

% --- Integral capture, fission and production spectra:

det 5 de 1 dt -1 dr -2 void
det 6 de 1 dt -1 dr -6 void
det 7 de 1 dt -1 dr -7 void

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