Doubts with the MCNP software for my thesis

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SUMMARY

The forum discussion centers on troubleshooting a "fatal error" message encountered in the MCNP (Monte Carlo N-Particle Transport Code) software, specifically the error stating "fatal error. facet 1.0 of tally 1 does not exist." The user, Geovanny, is attempting to calculate a f1 tally on a surface that is not defined in their input file. The conversation highlights the importance of ensuring that all geometries and surfaces are correctly specified in the input file, as indicated in the MCNP manual (page 4-15) regarding geometry rotation.

PREREQUISITES
  • Understanding of MCNP software and its functionalities
  • Familiarity with input file structure in MCNP
  • Knowledge of geometry definitions in MCNP
  • Basic principles of tally calculations in MCNP
NEXT STEPS
  • Review the MCNP manual, focusing on geometry definitions and error messages
  • Learn how to properly define and rotate geometries in MCNP
  • Explore common MCNP fatal errors and their solutions
  • Practice creating and debugging MCNP input files with various tally types
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Students and researchers in nuclear physics, particularly those using MCNP for simulations, as well as educators teaching computational methods in radiation transport.

Geovanny Gutierrez
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Hello, it's a privilege to enter in this forum. My name is Geovanny, I'm from Mexico and I'm a student from the Autonomous Yucatan University. I'm studying in my last semester of Physical Engineering and i have some doubts about de MCNP software.

One of those is the next message that VISEDX give me when i try to open my code: "fatal error. facet 1.0 of tally 1 does not exist." I don´t know what exactly means these message. I hope this question isn´t silly.

Thank´s and nice to meet you.

<moved to nuclear physics>
 
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Hi,
Difficult to help you with no input file.
I suppose that you try to calculate a f1 tally on a surface but this surface is not describe in your input file.
 
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PSRB191921 said:
Hi,
Difficult to help you with no input file.
I suppose that you try to calculate a f1 tally on a surface but this surface is not describe in your input file.

Sorry, you're right, i'll give you my input file to review it. I was thinking that the problem is in my cell card but I've been checking the file and don't find some error because VISED plot my geometry. Thanks a lot.

upload_2018-10-4_10-17-41.png
upload_2018-10-4_10-18-13.png

upload_2018-10-4_10-19-15.png
 

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Geomtry 15 is strange
15 1 rcc ? I think it is the problem
It is better if you put your file in ascii in this forum
 
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The geometry 15 is a rigth circular cilinder at the middle of the canon rotated 135 degrees. I found in the MCNP manual (page 4-15) that´s the way to rotate the geometry, maybe i use it in a wrong way. Here's my code:

Fuente Cañon_Completo
c
c ******** Tarjeta de Cel *********
c
1 1 -7.874 -15 imp:e=1
2 0 (-1:-3:-5) 15 imp:e=1
3 1 -7.874 (-2:-4:-6:-8:-9:-10:-11:-12:-13) 1 3 5 imp:e=1
4 1 -7.874 2 4 6 8 9 10 11 12 13 -7 imp:e=1
5 2 -0.001205 2 4 6 7 8 9 10 11 12 13 -14 imp:e=1
6 3 -3.35 14 imp:e=1
c

c ****** Tarjeta de Superficie *****
c
1 RCC 0 0 0 84.3 0 0 1.85
2 RCC 0 0 0 84.3 0 0 2
3 RCC 37.8 0 0 0 9 0 1.85
4 RCC 37.8 0 0 0 9 0 2
5 RCC 37.8 0 0 0 -9 0 1.85
6 RCC 37.8 0 0 0 -9 0 2
7 RPP 84.3 89.3 -2.5 2.5 -1.5 1.5
8 RCC 0 0 0 1.2 0 0 3
9 RCC -1.2 0 0 1.2 0 0 3
10 RCC 37.8 7.8 0 0 1.2 0 3
11 RCC 37.8 9 0 0 1.2 0 3
12 RCC 37.8 -9 0 0 1.2 0 3
13 RCC 37.8 -10.2 0 0 1.2 0 3
14 BOX -142.5 -100 -100 285 0 0 0 200 0 0 0 200
15 1 RCC 0 0.90057 0 1.80114 0 0 0.2
c

c ******** Tarjeta de Datos ********
c
c $ Pantalla central angulada 135 sobre el eje x
c
TR1 38.7 0 0 -0.707 0.707 0 -0.707 -0.707 0 0 0 1
c
MODE e
c
c FUENTE PUNTUAL
SDEF POS=86.3 0 0 AXS=-1 0 0 RAD=d1 PAR=3 ERG=0.08 VEC=-1 0 0 DIR=1
SI1 0 1.85
SP1 -21 1
c
c MATERIALES
c
c Air (0.001205 g/cm^3)
M2 6000 -0.000124 &
7014 -0.755268 &
8016 -0.231781 &
18000 -0.012827
c
c Barite Concrete (3.35 g/cm^3)
M3 1001 -0.003585 &
8016 -0.311622 &
12000 -0.001195 &
13027 -0.004183 &
14000 -0.010457 &
16000 -0.107858 &
20000 -0.050194 &
26000 -0.047505 &
56138 -0.463400
c
c Iron (7.874 g/cm^3)
M1 26000 -1.000000
c
c TALLY
c
f1:e (1 3 5) (7 15) T
f2:e (1 3 5) (7) 15
f4:e 1 4
c Energia inicial, conteos, Energia final (Tally energy)
E0 0 500i 0.08
c
NPS 1e7
prdmp 1e7 1e6 0 1
print
c
c
c Fin
 

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