Recent content by Gogy
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Calculation of activation with mesh tally in MCNPX 2.6
Alex, it was great! I had splitted your mesh for 10x10x10. Then in a void geometry for elementary cell of the mesh at the 90 cm distance from the point isotropic source a flux was determined (9.70884E-6 vs 9.824E-6 for 1/R^2 dependence). Accepted. Inspecting of 13027.24y reveals a meaning of...- Gogy
- Post #6
- Forum: Nuclear Engineering
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Calculation of activation with mesh tally in MCNPX 2.6
Thank you, Alex, for your trying to help! Here is an example. It can show a principal problem. Of course, *****.24y is an old library, but it's structure is the same that newer libs have. 24y here is only for example.- Gogy
- Post #3
- Forum: Nuclear Engineering
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Calculation of activation with mesh tally in MCNPX 2.6
Hi, All! Can anyone help me to construct a card for calculation of a spatial activation? Reaction is 27Al(n,p). I used a tmesh card for calculation of neutron flux as: tmesh rmesh21:n flux cora21 190 9i 210 corb21 -10 9i 10 corc21 -10 9i 10 ergsh21 0 20 endmd Somewhere in a problem I...- Gogy
- Thread
- Activation Calculation Mcnpx Mesh
- Replies: 5
- Forum: Nuclear Engineering