Doubts with the MCNP software for my thesis

In summary, Geovanny from Mexico and a student from the Autonomous Yucatan University is studying in his last semester of Physical Engineering and has some doubts about the MCNP software. One of his doubts is regarding an error message that he receives when trying to open his code. He has searched online for solutions and found a presentation that may provide additional insight. He also shares his input file for review and asks for help in identifying the error. The conversation also includes discussions about the geometry and materials used in the code, as well as the tally and energy settings. The code ends with a request for assistance in finding the error.
  • #1
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>
 
Last edited by a moderator:
Engineering news on Phys.org
  • #3
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.
 
  • Like
Likes Geovanny Gutierrez
  • #5
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 becuase 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
 

Attachments

  • upload_2018-10-4_10-15-47.png
    upload_2018-10-4_10-15-47.png
    7.6 KB · Views: 508
  • upload_2018-10-4_10-17-41.png
    upload_2018-10-4_10-17-41.png
    3.1 KB · Views: 728
  • upload_2018-10-4_10-18-13.png
    upload_2018-10-4_10-18-13.png
    4.5 KB · Views: 790
  • upload_2018-10-4_10-19-15.png
    upload_2018-10-4_10-19-15.png
    2.1 KB · Views: 659
  • #6
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
 
  • Like
Likes Geovanny Gutierrez
  • #7
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
 

1. What is MCNP software and how does it work?

MCNP (Monte Carlo N-Particle) is a general-purpose Monte Carlo radiation transport code used to simulate the behavior of particles as they interact with matter. It is commonly used in nuclear engineering, medical physics, and other fields to model complex radiation interactions. The software works by using random number generators to simulate the behavior of individual particles as they move through a given geometry and interact with materials.

2. How can I ensure the accuracy of my results using MCNP?

To ensure the accuracy of your results, it is important to carefully define your problem and input parameters, use appropriate models and cross-section data, and run multiple simulations with different settings to evaluate any uncertainties. It is also recommended to compare your results with experimental data, if available, to validate the accuracy of your simulation.

3. Can MCNP handle all types of radiation interactions?

MCNP is capable of simulating a wide range of radiation interactions, including neutron, photon, electron, and positron interactions. It can also simulate interactions with various materials such as water, tissue, and metals. However, it is important to carefully consider the limitations and assumptions of the software for your specific application.

4. How can I troubleshoot any issues or errors with MCNP?

If you encounter any issues or errors with MCNP, it is recommended to consult the user manual, online forums, or contact the developers for assistance. It is also helpful to carefully review your input parameters and settings to ensure they are correct and appropriate for your problem.

5. Are there any alternative software programs to MCNP?

While MCNP is a widely used and trusted software for radiation transport simulations, there are other similar programs available such as Geant4 and FLUKA. It is important to research and evaluate different options to determine which software best suits your specific needs and research goals.

Suggested for: Doubts with the MCNP software for my thesis

Replies
17
Views
811
Replies
1
Views
749
Replies
2
Views
1K
Replies
4
Views
990
Replies
2
Views
849
Replies
1
Views
731
Replies
1
Views
995
Back
Top