Recent content by NuclearEng12
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Solving "Fatal Error" in MCNPX Input Code
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...- NuclearEng12
- Post #3
- Forum: Nuclear Engineering
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Solving "Fatal Error" in MCNPX Input Code
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.- NuclearEng12
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- Error Mcnpx
- Replies: 2
- Forum: Nuclear Engineering
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Error: Bad Trouble in IMCN - Unexpected EOF
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...- NuclearEng12
- Thread
- Error
- Replies: 6
- Forum: Nuclear Engineering
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I am a beginner user of MCNP and is still learning how to use it. When
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.- NuclearEng12
- Post #13
- Forum: Nuclear Engineering
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I am a beginner user of MCNP and is still learning how to use it. When
Thanks for the pointers. It will really help me.- NuclearEng12
- Post #10
- Forum: Nuclear Engineering
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I am a beginner user of MCNP and is still learning how to use it. When
You have to request it from Oak Ridge i think.- NuclearEng12
- Post #7
- Forum: Nuclear Engineering
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I am a beginner user of MCNP and is still learning how to use it. When
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...- NuclearEng12
- Post #5
- Forum: Nuclear Engineering
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I am a beginner user of MCNP and is still learning how to use it. When
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 =...- NuclearEng12
- Post #3
- Forum: Nuclear Engineering
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I am a beginner user of MCNP and is still learning how to use it. When
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.- NuclearEng12
- Thread
- Beginner Mcnp
- Replies: 12
- Forum: Nuclear Engineering