Recent content by ameermukhtar
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MCNPX output proton energy is zero?
please find attach here my output file with f6:h 1 2 3 4 5 6 7 8 9 but cell 4 5 6 7 is value of h is zero- ameermukhtar
- Post #8
- Forum: Nuclear Engineering
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MCNPX output proton energy is zero?
- ameermukhtar
- Post #6
- Forum: Nuclear Engineering
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MCNPX output proton energy is zero?
- ameermukhtar
- Post #5
- Forum: Nuclear Engineering
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MCNPX output proton energy is zero?
i also changed but the result is same i.e i can not get the values for f6:p1 2 3 4 5 6 7 8 9- ameermukhtar
- Post #4
- Forum: Nuclear Engineering
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MCNPX output proton energy is zero?
Hello everyone please look on these input and out put file in the files neutron400. txt and neutron400.out i am facing a problem. in neutron400.out when you will see the output than you will see that f6:n1 2 3 4 5 6 7 8 9 etc.... but in the same time f6:p1 2 3 4 5 6 7 8 9 is zero and i want...- ameermukhtar
- Thread
- Replies: 8
- Forum: Nuclear Engineering
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Reflector flux contribution
my neutrons production is in cell 3 and i need the flux at the end of the cell 7- ameermukhtar
- Post #5
- Forum: Nuclear Engineering
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Reflector flux contribution
yes you are right. BSA means " Beam Shape Assembly" . and you are right i want flux 5e8. acutually i am doing Boron neutron capture therapy- ameermukhtar
- Post #3
- Forum: Nuclear Engineering
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Reflector flux contribution
Hi this is the attached file . i want to get the flux at the end of BSA which is cell 7 also the flux of cell 8 is less than 5e8. now my target is to get the flux greater than 5e8. thank you to all- ameermukhtar
- Thread
- Replies: 4
- Forum: Nuclear Engineering
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Help with error in MCNP6: "Geometry error: no intersection found"
sir i red the my input file now a time i don't need de5 and df5 but i need these factors 𝜙epithermal (n/cm2s) × 109 𝜙epithermal/𝜙thermal D˙f/𝜙epithermal (Gy cm2) × 10−13 D˙𝛾/𝜙epithermal (Gy cm2) × 10−13 and now here is my input file attached and last things that sir how to attach the tally of df5?- ameermukhtar
- Post #8
- Forum: Nuclear Engineering
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Help with error in MCNP6: "Geometry error: no intersection found"
sir where is input modify file- ameermukhtar
- Post #7
- Forum: Nuclear Engineering
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Help with error in MCNP6: "Geometry error: no intersection found"
this is my input file- ameermukhtar
- Post #5
- Forum: Nuclear Engineering
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Help with error in MCNP6: "Geometry error: no intersection found"
today i again run this file and edit but i am not successful here i am attached the file- ameermukhtar
- Post #4
- Forum: Nuclear Engineering
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Help with error in MCNP6: "Geometry error: no intersection found"
here is input- ameermukhtar
- Post #2
- Forum: Nuclear Engineering
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Help with error in MCNP6: "Geometry error: no intersection found"
Geometry error: no intersection found. run terminated because 10 particles got lost. please anyone can help me- ameermukhtar
- Thread
- Replies: 7
- Forum: Nuclear Engineering
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MCNP6 Error: "Geometry error: no cell found"
thank you dear the problem has been solved- ameermukhtar
- Post #4
- Forum: Nuclear Engineering