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I am a beginner user of MCNP and is still learning how to use it. When

  1. May 19, 2012 #1
    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.
     
  2. jcsd
  3. May 21, 2012 #2

    QuantumPion

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    Re: Mcnp

    Try searching for error messages in the output file. If you have no output file at all, verify that you have installed the software correctly. The package should have included some test cases which you can run to verify that MCNP is correctly installed.
     
  4. May 21, 2012 #3
    Re: Mcnp

    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 = 111194823047613

    zero lattice element hit.
    1problem summary

    run terminated because of bad trouble.
     
  5. May 21, 2012 #4

    QuantumPion

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    Re: Mcnp

    It sounds like you have defined a lattice but not all of the elements are filled, or you have filled an array element with an invalid universe. Check your fill and lattice cards and make sure they are set up correctly.
     
  6. May 22, 2012 #5
    Re: Mcnp

    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 $ ZIRLO Cladding
    4 4 -0.727 3 u=1 imp:n=1 $ Water/ Coolant
    5 4 -0.727 -11 u=2 imp:n=1 $ Outside Fuel Element
    6 0 -4 5 -7 6 LAT=1 u=3 imp:n=1 Fill=-9:9 -9:9 0:0
    2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 $ Physical Boundary
    2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 $ Row 1
    2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 $ Row 2
    2 1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1 2 $ Row 3
    2 1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1 2 $ Row 4
    2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 $ Row 5
    2 1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 $ Row 6
    2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 $ Row 7
    2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 $ Row 8
    2 1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 $ Row 9
    2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 $ Row 10
    2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 $ Row 11
    2 1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 $ Row 12
    2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 $ Row 13
    2 1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1 2 $ Row 14
    2 1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1 2 $ Row 15
    2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 $ Row 16
    2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 $ Row 17
    2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 $ Physical Boundary
    7 0 15 14 -12 -13 8 -10 Fill=3 u=4 imp:n=1 $ Lattice Physical Boundary
    8 4 -0.727 -16 u=5 imp:n=1 $ Outside Assembly
    9 0 14 -12 -13 15 LAT=1 u=6 imp:n=1 Fill=-8:8 -8:8 0:0
    2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 $ Physical Boundary
    2 2 2 2 2 2 2 3 3 3 2 2 2 2 2 2 2 $ Row 1
    2 2 2 2 2 3 3 3 3 3 3 3 2 2 2 2 2 $ Row 2
    2 2 2 2 3 3 3 3 3 3 3 3 3 2 2 2 2 $ Row 3
    2 2 2 3 3 3 3 3 3 3 3 3 3 3 2 2 2 $ Row 4
    2 2 3 3 3 3 3 3 3 3 3 3 3 3 3 2 2 $ Row 5
    2 2 3 3 3 3 3 3 3 3 3 3 3 3 3 2 2 $ Row 6
    2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 2 $ Row 7
    2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 2 $ Row 8
    2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 2 $ Row 9
    2 2 3 3 3 3 3 3 3 3 3 3 3 3 3 2 2 $ Row 10
    2 2 3 3 3 3 3 3 3 3 3 3 3 3 3 2 2 $ Row 11
    2 2 2 3 3 3 3 3 3 3 3 3 3 3 2 2 2 $ Row 12
    2 2 2 2 3 3 3 3 3 3 3 3 3 2 2 2 2 $ Row 13
    2 2 2 2 2 3 3 3 3 3 3 3 2 2 2 2 2 $ Row 14
    2 2 2 2 2 2 2 3 3 3 2 2 2 2 2 2 2 $ Row 15
    2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 $ Physical Boundary
    10 0 -17 8 -10 Fill=6 imp:n=1 $ Lattice Physical Boundary
    11 0 17:-8:10 imp:n=0 $ Outside Core

    c Surface Cards
    1 cz .410
    2 cz .418
    3 cz .475
    4 px .630
    5 px -.630
    6 py -.630
    7 py .630
    8 pz 0
    9 pz 366
    10 pz 400
    11 cz 100
    12 px 10.71
    13 py 10.71
    14 px -10.71
    15 py -10.71
    16 cz 500
    17 cz 199.4

    c Data Cards
    m1 92235.70c -0.003338 92238.70c -0.063422 8016.70c -0.008980 $ 5% Enriched UO2 Fuel
    92235.71c -0.040734 92238.71c -0.773946 8016.71c -0.109580
    m2 2004.70c -0.07574 $ Helium
    2004.71c -0.92426
    m3 40090.70c 0.038189 40091.70c 0.008328 40092.70c 0.012730 $ ZIRLO Cladding
    40094.70c 0.012900 40096.70c 0.002078 50112.70c 0.000007
    50114.70c 0.000005 50115.70c 0.000003 50116.70c 0.000110
    50117.70c 0.000058 50118.70c 0.000183 50119.70c 0.000065
    50120.70c 0.000247 50122.70c 0.000035 50124.70c 0.000044
    41093.70c 0.000757 40090.71c 0.466021 40091.71c 0.101628
    40092.71c 0.155340 40094.71c 0.157424 40096.71c 0.025362
    50112.71c 0.000090 50114.71c 0.000061 50115.71c 0.000031
    50116.71c 0.001344 50117.71c 0.000710 50118.71c 0.002239
    50119.71c 0.000794 50120.71c 0.003011 50122.71c 0.000428
    50124.71c 0.000535 41093.71c 0.009243
    m4 1001.70c 0.050487 1002.70c 0.000006 8016.70c 0.025247 $ H2O
    1001.71c 0.616102 1002.71c 0.000071 8016.71c 0.308087
    kcode 1000 1.0 20 120
    ksrc 1.26 0 183
    44.1 -86.94 183
    86.94 -22.68 183
    22.68 -44.1 183
    108.36 -86.94 183
    129.78 1.26 183
    44.1 44.1 183
    86.94 65.52 183
    65.52 108.36 183
    22.68 65.52 183
    -86.94 86.94 183
    -22.68 22.68 183
    -65.52 65.52 183
    -22.68 151.2 183
    -1.26 0 183
    -1.26 -86.94 183
    -65.52 -44.1 183
    -44.1 -22.68 183
    -151.2 -22.68 183
    -86.94 -44.1 183
    PRINT 128
     
  7. May 23, 2012 #6
    Re: Mcnp

    how do i get my hands on the MCNP code?
     
  8. May 23, 2012 #7
    Re: Mcnp

    You have to request it from Oak Ridge i think.
     
  9. May 23, 2012 #8

    QuantumPion

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    Re: Mcnp

    It looks to me like you are not defining your lattices correctly, or at least the surfaces the cells are assigned to. It looks like you are trying to use universe 2 for both a reflector region as well as a guide tube region although their geometry does not match. Maybe you meant to use universe 5 for this purpose since it is not used anywhere.
     
    Last edited: May 23, 2012
  10. May 23, 2012 #9

    QuantumPion

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    Re: Mcnp

    I don't have an example of a whole core case, I think that would run very very slowly on my computer :(
     
    Last edited: May 23, 2012
  11. May 23, 2012 #10
    Re: Mcnp

    Thanks for the pointers. It will really help me.
     
  12. May 23, 2012 #11

    Astronuc

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    Re: Mcnp

    So one is trying to model a 17x17 lattice with a 366 cm active fuel zone. There are 157 assemblies in the core.

    2 is in the lattice map is water. The guide tube and water between assemblies would have different geometries and size.

    The densities in the cell cards seem correct, and the radial and axial dimensions in the fuel rods and the cell pitch of ~12.6 cm seem correct. Above the active fuel zone would be the plenum (filled with He and stainless steel spring ~ 0.09 - 0.15 of the void volume with a height of about 20 cm). There are upper and lower endplugs (Zr-4 or ZIRLO) and stainless steel nozzle below and above the core.

    It looks like you might have some gad in there. BTW - 5% is a bit high for a fresh core, without extensive holddown.
     
  13. May 23, 2012 #12

    Astronuc

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    Re: Mcnp

    Access is restricted and usually limited to government facilities, e.g., DOE labs, universities and corporations who a then subject to export controls.
     
  14. May 25, 2012 #13
    Re: Mcnp

    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.
     
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