The geometry of the pin

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The geometry of the pin

Postby rungomega » Wed Oct 17, 2018 1:48 am

Hi !!! Can you show me how to build in SERPENT 2 this pin?
Thank you very much !!!
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Screenshot_2.jpg
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rungomega
 
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Joined: Sat Dec 23, 2017 4:39 pm

Re: The geometry of the pin

Postby Ramzy1990 » Mon Oct 22, 2018 9:01 pm

Hey there,

Maybe you can use a combination of rounded crosses and cylinders ( See http://serpent.vtt.fi/mediawiki/index.php/Surface_types ) to define your exact geometry. Cylinders would be needed for the sharp edges left inside the crosses boundaries (See the attached figure). Here is an input file that should work with just rounded crosses case. I have included some information inside of it too (I am a bit newbie to Serpent, and possibly this is not the best way to do the different universe filling thing, which is for facilitating Xsecs generation for different universes).

UnitCell_geom3.png
Plot for the design reported in the input file
UnitCell_geom3.png (5.25 KiB) Viewed 56 times


Code: Select all
set title HelicalFuelUnitCell

% ----- Input File

%%%%%%%%%%%%%%%%%%%%%%%%%%
% --- Surfaces
%%%%%%%%%%%%%%%%%%%%%%%%%%

% ----- Two infinite crosses along the z-axis. You use the rounded corner definition in Serpent Wiki.
% ----- Bound them all with a cube to be able to do repititive BCs, and omit the protions not needed in the z-axis.
% ----- According to Serpent manual, you have to have something like that (a shape and not individual planes) to apply repititive BCs.

surf sf inf               % Needed for different universes filling according to what I understood from Serpent manual page 35
surf sc inf               % Needed for different universes filling according to what I understood from Serpent manual page 35

cell cf 2 Fuel -sf         % Needed for different universes filling according to what I understood from Serpent manual page 35
cell cc 3 Clad -sc         % Needed for different universes filling according to what I understood from Serpent manual page 35

surf s1 cross  0.0  0.0  0.6546  0.1461  0.1461       % Cross parallel to the z-axis (x0, y0, l, d, s)
surf s2 cross  0.0  0.0  0.7359  0.2274  0.2274         % Cross parallel to the z-axis (x0, y0, l, d, s)

surf s3 cuboid    -1.0  1.0  -1.0  1.0 -10.0 10.0       % Cube (-x, x, -y, y, -z, z)


%%%%%%%%%%%%%%%%%%%%%%%%%%
% --- Cells
%%%%%%%%%%%%%%%%%%%%%%%%%%

% ----- Fuel is given inside the cube, and inside the inner cross s1 above.
% ----- Cladding out of the fuel surface s1 and inside the outer cross surface s2.
% ----- You can change the void material in the next definition to something like water for e.g.
% ----- We need to use the filling method for defining different universes (for Cross-sections generation).
% ----- Outside is anything outside the cube surface s3.

cell c1 1 fill 2  -s3 -s1
cell c2 1 fill 3  -s2 s1
cell cv 1 void    -s3 s2
cell c3 1 outside  s3

cell ccube 0 fill 1      -s3
cell c4 0  outside       s3

%%%%%%%%%%%%%%%%%%%%%%%%%%%
% --- material definitions
%%%%%%%%%%%%%%%%%%%%%%%%%%%

mat Fuel   -19.1 tmp 1000 rgb 45 47 50

92235.09c  -3.0
92238.09c  -97.0

mat Clad -7.88 rgb 185 183 127
26000.09c -100.0

set acelib "/cm/shared/apps/ncsu/SERPENT/xsdata/jeff311/sss_jeff311u.xsdata"

%%%%%%%%%%%%%%%%%%%%%%%%%%
% --- Run Parameters
%%%%%%%%%%%%%%%%%%%%%%%%%%

% ----- Neutron population: neutrons per cycle, active / inactive cycles
set pop 10000 100 10

% ----- Boundary condition (1 = black, 2 = reflective, 3 = periodic)
set bc 2

%%%%%%%%%%%%%%%%%%%%%%%%%%
% --- Plot Parameters
%%%%%%%%%%%%%%%%%%%%%%%%%%

%The first value defines the plot plane (1 = yz, 2 = xz, 3 = xy).
%The second Value defines the plot boundaries (1 = cell boundaries, 2 = Material Boundaries, 3 = Both).

% --- Geometry and mesh plots:
plot 12 1000 1000
plot 22 1000 1000
plot 32 1000 1000
mesh 1  1000 1000
mesh 2  1000 1000
mesh 3  1000 1000
Ramzy1990
 
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