MCNP Help: 10 Particles Lost

AI Thread Summary
The discussion addresses a geometry error in MCNP when attempting to plot neutron and photon flux from radiation sources. The error message indicates that ten particles were lost due to a "no cell found" issue. A suggested solution is to remove the calculation point at the origin (0,0,0) to resolve the error. The user is advised to adjust the F5 and F15 commands accordingly to ensure proper execution of the code. This adjustment aims to facilitate successful plotting of flux as the source locations are moved further away.
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In my intro class, I am trying to design for radiation sources. Currently, I am trying to plot the flux from neutron and photon source locations progressively moving further and further away, however the code is not running and it says "geometry error: no cell found run terminated because 10 particles got lost."
 

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Hi,
you are trying to calculate an F5 (and F15) at (0,0,0) where your neutrons are emitted. Try to remove this calculation point, like this :
F5:N 10 0 0 1
20 0 0 1
30 0 0 1
40 0 0 1
50 0 0 1
60 0 0 1
70 0 0 1
80 0 0 1
90 0 0 1
100 0 0 1
110 0 0 1
120 0 0 1
130 0 0 1
140 0 0 1
150 0 0 1
 
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