I have been trying to get this to run. It is a simple shielding experiment, with a neutron point source, concrete slab and a sphere as the detector. I have tried everything I know to fix this, but my limited knowledge of MCNP is making it hard to debug the code.
Hi Michael,
Please see the attached file. I recommend that you should refersomerefer some examples or carefully read the errors that appear on the commander (Terminal).
sincerely,
Your file has 2 problems.
1) the definition of cell 3, if do not want to use the complement operator # as already suggested, should read as follows:
3 1 -0.001205 -1 (-2:3:-4:5:-6:7) 8
in other words, you have to intersect the interior of the big sphere with the exterior of the slab (represented by the parentheses and the detector.
2) as reported in the manual: "If the first five columns of a card are blank, the entries on the card are interpreted as a continuation of the data from the last named card." The material section does not respect this rule and the line starting with 12000 is not interpreted as a continuation of the "material 2" definition.
Attached a working file
Regards
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