Recent content by NuclearEng12

I have done all of those things. It is still giving me the same error. Could there be another cause? Identifier Reaction Rate c c c cell cards 5 5 -8.57 -1 2 -5 u=1 imp:n=1 VOL=0.0025 $ Niobium-94 6 6 -1.93 -1 2 5 -6 u=1 imp:n=1 VOL=0.0075 $ Cesium-137 7 7...

I am running a simple MCNPX input code and am getting a fatal error that says: "Fatal Error: no m card for material no. X". I thought it was something with my data card or my cell cards but can not figure out what the problem is.

I am getting an error which reads as follows: "bad trouble in imcn in routine pass1 unexpected eof in file ****** " I just added a sdef and nps card to my input file, so I assumed the error was with one of those. SDEF AXS=0 0 1 ERG=D1 RAD=D2 WGT=1 TME=0 PAR=1 SI1 0 .4...

I have corrected the universes in the 2nd lattice by replacing universe 2 with universe 5 however it is still saying 'Zero Lattice Element Hit'. I looked at the code closely and still have no idea what the problem is.

Thanks for the pointers. It will really help me.

You have to request it from Oak Ridge i think.

I have reviewed my input file and can not identify where I might have went wrong. c Cell Cards 1 1 -10.41 -1 -9 u=1 imp:n=1 $ Fuel Pellet 2 2 -0.130 (1 -2 -9):(9 -2) u=1 imp:n=1 $ Helium Gap 3 3 -6.52 2 -3 u=1 imp:n=1...

The following are the error messages I am getting warning. print table 128 requires 1088303 dec. words of storage. bad trouble in subroutine newcel of mcrun source particle no. 672 starting random number =...

I am a beginner user of MCNP and is still learning how to use it. When I run my program, I get a message that says 'bad trouble in subroutine main of mcnp'. What exactly does that mean and how can i correct it. Thanks.