- #1
Deb
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- TL;DR Summary
- I woud like to calcultate a dose (with an F2 tally) through a surface with MCNP6.2 and the code cannot calcute the area of the surface.
Hello,
after many simplifications my geometry has become very simple: just a box of concrete with a cylinder of steel inside. The source is outside in the air. The cell and the surface cards are like the following:
C ******************Block 1: Cells**********************
100 0 99 imp:p=0
99 1 -0.00122 (-99 2.3):( -99 2.2) imp:p=1 $ Air
1 2 -2.3 -99 2 -2.3 -2.2 imp:p=1 $ Concrete
2 3 -7.6 -2 imp:p=1 $ Cylinder (steel)
C *******************Block 2: Surfaces**************************
99 RPP 0.0 450.0 50.0 172.0 50.0 172.0
2 RCC 270.0 111.0 111.0 140.0 0.0 0.0 4.5
I attach a picture of the geometry.
In the output file I have this message:
surface input calculated reason area
area area not calculated
2 99.1 0.00000E+00 1.48840E+04
3 99.2 0.00000E+00 1.48840E+04
4 99.3 0.00000E+00 5.49000E+04
5 99.4 0.00000E+00 5.49000E+04
6 99.5 0.00000E+00 5.49000E+04
7 99.6 0.00000E+00 5.49000E+04
9 2.1 0.00000E+00 3.95841E+03
10 2.2 0.00000E+00 0.00000E+00 asymmetric
11 2.3 0.00000E+00 0.00000E+00 asymmetric
I guess that the areas of the surfaces 2.2 2.3 are not calculated because they are used both as basis for the cylinder and for closing the concrete box. Therefore MCNP cannot distinguish which size he has to assign to the surfaces.
I want to calculate the dose (with an F2 tally) at the entrance and at the exit of the concrete, which means through the surface 22.2 and 22.3, whose area is not automatically calculated. I could use the SD card to pass the correct area to the code.
-My first question is: the particle flux is calculated through the two basis of the cylinder or through the two rectangles closing the concrete box?
-Second question: is there a way to solve this problem? I have tried also using two the px planes to close the concrete cell, but this does not help, since MCNP cancel the identical surfaces.
Thanks to anyone, who can help me.
Debora
after many simplifications my geometry has become very simple: just a box of concrete with a cylinder of steel inside. The source is outside in the air. The cell and the surface cards are like the following:
C ******************Block 1: Cells**********************
100 0 99 imp:p=0
99 1 -0.00122 (-99 2.3):( -99 2.2) imp:p=1 $ Air
1 2 -2.3 -99 2 -2.3 -2.2 imp:p=1 $ Concrete
2 3 -7.6 -2 imp:p=1 $ Cylinder (steel)
C *******************Block 2: Surfaces**************************
99 RPP 0.0 450.0 50.0 172.0 50.0 172.0
2 RCC 270.0 111.0 111.0 140.0 0.0 0.0 4.5
I attach a picture of the geometry.
In the output file I have this message:
surface input calculated reason area
area area not calculated
2 99.1 0.00000E+00 1.48840E+04
3 99.2 0.00000E+00 1.48840E+04
4 99.3 0.00000E+00 5.49000E+04
5 99.4 0.00000E+00 5.49000E+04
6 99.5 0.00000E+00 5.49000E+04
7 99.6 0.00000E+00 5.49000E+04
9 2.1 0.00000E+00 3.95841E+03
10 2.2 0.00000E+00 0.00000E+00 asymmetric
11 2.3 0.00000E+00 0.00000E+00 asymmetric
I guess that the areas of the surfaces 2.2 2.3 are not calculated because they are used both as basis for the cylinder and for closing the concrete box. Therefore MCNP cannot distinguish which size he has to assign to the surfaces.
I want to calculate the dose (with an F2 tally) at the entrance and at the exit of the concrete, which means through the surface 22.2 and 22.3, whose area is not automatically calculated. I could use the SD card to pass the correct area to the code.
-My first question is: the particle flux is calculated through the two basis of the cylinder or through the two rectangles closing the concrete box?
-Second question: is there a way to solve this problem? I have tried also using two the px planes to close the concrete cell, but this does not help, since MCNP cancel the identical surfaces.
Thanks to anyone, who can help me.
Debora