The forum discussion centers on resolving a geometry error in an MCNP input deck, specifically related to cell #14, which represents the outer edge of a detector model. The user seeks assistance in defining a union of surfaces for this cell, emphasizing the importance of precision in surface definitions. The discussion highlights a quick fix involving the use of the "imp:p" command to negate a cell, ensuring that the boundary to the void is correctly established without interfering with volumes defined by other cells.
PREREQUISITESThis discussion is beneficial for nuclear engineers, radiation physicists, and researchers using MCNP for simulations, particularly those dealing with complex geometries and seeking to optimize their input decks.
14 0 -99 #1 #2 #3 #4 #5 #6 #7 #8 #9 #10 #11 #12 imp:p 1 $ surroundings