Mcnp Error
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Community Forums > Engineering > Nuclear Engineering > We've just passed 300 Insights! View them here! What a resource! Dismiss Notice Dismiss Notice Join Physics Forums Today! The friendliest, high quality science and math community on the planet! Everyone who loves science is mcnp continue run here! Fatal Error in MCNPX Dec 30, 2012 #1 NuclearEng12 I am running a simple MCNPX mcnp source examples input code and am getting a fatal error that says: "Fatal Error: no m card for material no. X". I thought it was
Mcnp Error Messages
something with my data card or my cell cards but can not figure out what the problem is. NuclearEng12, Dec 30, 2012 Phys.org - latest science and technology news stories on Phys.org •Game over? Computer beats human champ in
Mcnp Input File Example
ancient Chinese game •Simplifying solar cells with a new mix of materials •Imaged 'jets' reveal cerium's post-shock inner strength Dec 31, 2012 #2 Astronuc Staff: Mentor NuclearEng12 said: ↑ 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. Check the cell how to run mcnp input file cards and the corresponding material card. Cell card syntax: j m d geom params j = cell number; 1 ≤ j ≤ 99999. m = 0 if the cell is a void. or,= material number if the cell is not a void. This indicates that the cell is to contain material m, which is specified on the Mm card. "Cell, surface, and data cards must all begin within the first five columns. Entries are separated by one or more blanks. Numbers can be integer or floating point. MCNP makes the appropriate conversion. A data entry item must be completed on one line. Blanks filling the first five columns indicate a continuation of the data from the last named card. An '&' (ampersand) ending a line indicates data will continue on the following card, where data on the continuation card can be in columns 1~80. MCNP makes extensive checks of the input file for user errors. A FATAL error occurs if a basic constraint of the input specification is violated, and MCNP will terminate before running any particles. The first fatal error is real; subsequent error messages may or may not be real because of the nature of the first fatal message." "The material specification gives a material number to be referenced by cell cards, the atomic number, the atomic mass and the weight fraction or the atomic fraction of each constituent (element) in the materi
Free Downloads Vised Gallery Consulting Output Visualization C++ Tips and Tricks Vised Video Demos. Gamma Spectroscopy Tools Zero Lattice Element Hit Error Occurs on
Mcnp Example Input Files
a Rotated Lattice. Anomaly: The run dies with a zero lattice element mcnp examples hit error when a lattice is rotated. History: Submitted by user. Versions affected: MCNP5, MCNPX, MCNP6 Impact: Fails mcnp tr card to run Work Around: Modify macrobody surfaces to remove chain warning. Steps required to reproduce this anomaly: Note: Run this example in the RSICC release of each of these codes. https://www.physicsforums.com/threads/fatal-error-in-mcnpx.661648/ About the Input file: A three by three xz lattice with a pitch of 20 cm. Each lattice cell is filled with an 8 cm radius sphere of water. A fixed source is volumetrically distributed through each of the nine spheres. A translation card rotates the lattice. Note the surface definition for surface 7 appears twice. The work-around definition http://www.mcnpvised.com/dontdothat/rotatelatticefail/rotatelatticefail.html is commented out. Click here to download the input file, iddt3 (2 kb). Process to Produce Anomaly: Verify that the surface definition for surface 7 is the : rpp -10 50 -10 10 -10 50 version of the input file. Run the input file in MCNP5 and/or MCNPX and/or MCNP6 verify the result. Work around: Verify that the surface definition for surface 7 is the : rpp -9.9999 49.9999 -9.9999 9.9999 -9.9999 40.9999 version of the input file. Click here to download the input file, iddt3a (2 kb). Process to Demonstrate Work Around.: Run the input file in MCNP5 and/or MCNPX and verify the result. Run the input file in MCNP6 and verify the results. Results obtained from our test: MCNP6 fails. Notice the two chain errors and that 6 surfaces were deleted. A zero lattice element hit error is displayed: With the surfaces moved, MCNP6 runs to completion: Notice the chain errors do not appear and only 2 surfaces were deleted. Runs to completion. Visual Editor Home
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