Hi. I need some help with the use of tally card in MCNP. I have been trying to use the f1, f4 and f2 tally to calculate surface current, average flux on a cell and avergage flux on a surface respectively, my question is: It's possible use those kind of tallies with macrobodies and surfaces...
The geometry 15 is a rigth circular cilinder at the middle of the canon rotated 135 degrees. I found in the MCNP manual (page 4-15) that´s the way to rotate the geometry, maybe i use it in a wrong way. Here's my code:
Fuente Cañon_Completo
c
c ******** Tarjeta de Cel *********
c
1 1 -7.874...
Sorry, you're right, i'll give you my input file to review it. I was thinking that the problem is in my cell card but I've been checking the file and don't find some error becuase VISED plot my geometry. Thanks a lot.
Hello, it's a privilege to enter in this forum. My name is Geovanny, I'm from Mexico and I'm a student from the Autonomous Yucatan University. I'm studying in my last semester of Physical Engineering and i have some doubts about de MCNP software.
One of those is the next message that VISEDX...