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
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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
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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...
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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
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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
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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
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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?
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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
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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
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    MCNP6 Error: "Geometry error: no cell found"

    thank you dear the problem has been solved
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