MCNP Help: 10 Particles Lost

[Optimus_Crime]

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."

 

[PSRB191921]

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