Particles transporting in MCNP5

In summary, MCNPX and MCNP6 are capable of simulating a wider range of particles compared to MCNP5, including exotic particles and the nucleus of atoms. Other programs such as GEANT4 and Fluka can also simulate these particles, but the best choice depends on the specific scenario and energy range. The user's goal of simulating stopping power in MCNP5 can be achieved by using a development version that was eventually discontinued. To compare results with GEANT4, the user can modify the input file and provide information on the particles, energy, target thickness and material. However, the results may vary depending on the stopping distance calculations and progress with the GEANT4 simulation. The provided output in GEANT4 shows the energy
  • #1
emilmammadzada
122
19
TL;DR Summary
particles,transport
Is it possible to transport only photon , electron and neutron in mcnp5?
 
Engineering news on Phys.org
  • #2
Yes.

MCNPX and MCNP6 (which is a merger of MCNPX and MCNP5) do a much wider range including exotic particles and the nucleus of a number of atoms, as will other programs, GEANT4 and Fluka for example. What is best to use depends on the situation, most people concentrating on low energy events, <20MeV for example probably wouldn't choose Fluka. If you were doing electron energy loss in thin films at a few KeV then the microelectronics module in GEANT4 might be the best at simulating.
 
  • Like
Likes emilmammadzada
  • #3
Alex A said:
Yes.

MCNPX and MCNP6 (which is a merger of MCNPX and MCNP5) do a much wider range including exotic particles and the nucleus of a number of atoms, as will other programs, GEANT4 and Fluka for example. What is best to use depends on the situation, most people concentrating on low energy events, <20MeV for example probably wouldn't choose Fluka. If you were doing electron energy loss in thin films at a few KeV then the microelectronics module in GEANT4 might be the best at simulating.
I want to simulate stopping power in mcnp5 and I want to find an example input file.I want to compare the results with geant4. I am using geant4
 
  • #4
What particle, what energy, how thick is the target, what is it made of?
 
  • Like
Likes emilmammadzada
  • #5
I want to send 5 MeV protons to my YZ=1mm and 10 um thickness chromium. How can I do this in mcnp5?
 
  • #6
There was a development version that did protons, but it was given up on. Unless you know you have it, MCNP5 does not do protons.

This is not quite what you asked for, it's a proton source with a 10um shell of chromium round it. Around that is a test cell I've given roughly unit volume. The result is not that meaningful, the f4 just confirms that less than 100 of the million fail to make it through. If you want to know energy loss information you'll need to modify it and/or tell us what your GEANT4 results are.

Code:
c Chromium 10um proton test.
1 0 -11
2 1 -7.19 11 -12
3 0 12 -13
4 0 13

c surfaces
11 so 1
12 so 1.001
13 so 1.07497

mode h
NPS 1000000
IMP:H 1 1 1 0
SDEF pos=0 0 0 erg=5.0 par=h
f4:h 3
M1 24050 0.04345
     24052 0.83789
     24053 0.09501
     24054 0.02365
 
  • Like
Likes emilmammadzada
  • #7
Alex A said:
Proton yapan bir geliştirme versiyonu vardı ama ondan vazgeçildi. Sahip olduğunuzu bilmediğiniz sürece, MCNP5 proton yapmaz.

Bu tam olarak istediğin şey değil, etrafında 10um'luk bir krom kabuğu olan bir proton kaynağı. Bunun çevresinde kabaca birim hacim verdiğim bir test hücresi var. Sonuç o kadar da anlamlı değil, f4 sadece bir milyonun 100'ünden daha azının bir çekirdekten sektiğini doğruluyor. Enerji kaybı bilgisini öğrenmek istiyorsanız, onu değiştirmeniz ve/veya GEANT4 sonuçlarınızın ne olduğunu bize bildirmeniz gerekir.

[kod]
c Krom 10um proton testi.
1 0 -11
2 1 -7.19 11 -12
3 0 12 -13
4 0 13

c yüzeyler
11 yani 1
12 yani 1.001
13 yani 1,07497

mod h
NPS 1000000
IMP:H 1 1 1 0
SDEF poz=0 0 0 erg=5,0 par=h
f4:h 3
M1 24050 0,04345
24052 0,83789
24053 0,09501
24054 0,02365

[/kod]
Thanks you very much .How can I see the stopping power in this code output?
 
  • #8
It depends on how you define stopping power. In terms of raw protons almost all of them make it through, presumably at reduced energy. What you can do with the code depends on if you can run it. Have you done stopping distance calculations so you have an idea what the results are supposed to look like? How far are you with the GEANT4 simulation?
 
  • Like
Likes emilmammadzada
  • #9
getesth1.png
getesth3.png
These are my result graphs in geant4
Depth(um)​
Energy loss​
Depth(um)1​
(atoms/cm^3)/(atoms/cm^2)​
5.00E-02​
2.20E+01​
0.05​
0.00​
1.50E-01​
2.20E+01​
0.15​
0.00​
2.50E-01​
2.21E+01​
0.25​
0.00​
3.50E-01​
2.20E+01​
0.35​
0.00​
4.50E-01​
2.20E+01​
0.45​
0.00​
5.50E-01​
2.19E+01​
0.55​
0.00​
6.50E-01​
2.19E+01​
0.65​
0.00​
7.50E-01​
2.20E+01​
0.75​
0.00​
8.50E-01​
2.20E+01​
0.85​
0.00​
9.50E-01​
2.20E+01​
0.95​
0.00​
1.05E+00​
2.20E+01​
1.05​
0.00​
1.15E+00​
2.20E+01​
1.15​
0.00​
1.25E+00​
2.21E+01​
1.25​
0.00​
1.35E+00​
2.21E+01​
1.35​
0.00​
1.45E+00​
2.21E+01​
1.45​
0.00​
1.55E+00​
2.21E+01​
1.55​
0.00​
1.65E+00​
2.20E+01​
1.65​
0.00​
1.75E+00​
2.20E+01​
1.75​
0.00​
1.85E+00​
2.21E+01​
1.85​
0.00​
1.95E+00​
2.21E+01​
1.95​
0.00​
2.05E+00​
2.21E+01​
2.05​
0.00​
2.15E+00​
2.21E+01​
2.15​
0.00​
2.25E+00​
2.21E+01​
2.25​
0.00​
2.35E+00​
2.21E+01​
2.35​
0.00​
2.45E+00​
2.21E+01​
2.45​
0.00​
2.55E+00​
2.21E+01​
2.55​
0.00​
2.65E+00​
2.21E+01​
2.65​
0.00​
2.75E+00​
2.21E+01​
2.75​
0.00​
2.85E+00​
2.22E+01​
2.85​
0.00​
2.95E+00​
2.22E+01​
2.95​
0.00​
3.05E+00​
2.21E+01​
3.05​
0.00​
3.15E+00​
2.23E+01​
3.15​
0.00​
3.25E+00​
2.22E+01​
3.25​
0.00​
3.35E+00​
2.22E+01​
3.35​
0.00​
3.45E+00​
2.22E+01​
3.45​
0.00​
3.55E+00​
2.22E+01​
3.55​
0.00​
3.65E+00​
2.23E+01​
3.65​
0.00​
3.75E+00​
2.22E+01​
3.75​
0.00​
3.85E+00​
2.23E+01​
3.85​
0.00​
3.95E+00​
2.23E+01​
3.95​
0.00​
4.05E+00​
2.23E+01​
4.05​
0.00​
4.15E+00​
2.23E+01​
4.15​
0.00​
4.25E+00​
2.23E+01​
4.25​
0.00​
4.35E+00​
2.23E+01​
4.35​
0.00​
4.45E+00​
2.22E+01​
4.45​
0.00​
4.55E+00​
2.23E+01​
4.55​
0.00​
4.65E+00​
2.23E+01​
4.65​
0.00​
4.75E+00​
2.23E+01​
4.75​
0.00​
4.85E+00​
2.23E+01​
4.85​
2.00​
4.95E+00​
2.23E+01​
4.95​
0.00​
5.05E+00​
2.24E+01​
5.05​
0.00​
5.15E+00​
2.23E+01​
5.15​
0.00​
5.25E+00​
2.23E+01​
5.25​
0.00​
5.35E+00​
2.24E+01​
5.35​
0.00​
5.45E+00​
2.24E+01​
5.45​
0.00​
5.55E+00​
2.24E+01​
5.55​
0.00​
5.65E+00​
2.24E+01​
5.65​
0.00​
5.75E+00​
2.23E+01​
5.75​
0.00​
5.85E+00​
2.23E+01​
5.85​
0.00​
5.95E+00​
2.24E+01​
5.95​
0.00​
6.05E+00​
2.23E+01​
6.05​
0.00​
6.15E+00​
2.23E+01​
6.15​
0.00​
6.25E+00​
2.25E+01​
6.25​
0.00​
6.35E+00​
2.24E+01​
6.35​
0.00​
6.45E+00​
2.25E+01​
6.45​
0.00​
6.55E+00​
2.24E+01​
6.55​
0.00​
6.65E+00​
2.24E+01​
6.65​
0.00​
6.75E+00​
2.24E+01​
6.75​
0.00​
6.85E+00​
2.24E+01​
6.85​
0.00​
6.95E+00​
2.24E+01​
6.95​
0.00​
7.05E+00​
2.26E+01​
7.05​
0.00​
7.15E+00​
2.24E+01​
7.15​
0.00​
7.25E+00​
2.25E+01​
7.25​
0.00​
7.35E+00​
2.25E+01​
7.35​
0.00​
7.45E+00​
2.26E+01​
7.45​
0.00​
7.55E+00​
2.24E+01​
7.55​
0.00​
7.65E+00​
2.25E+01​
7.65​
0.00​
7.75E+00​
2.24E+01​
7.75​
0.00​
7.85E+00​
2.25E+01​
7.85​
0.00​
7.95E+00​
2.25E+01​
7.95​
0.00​
8.05E+00​
2.26E+01​
8.05​
0.00​
8.15E+00​
2.26E+01​
8.15​
0.00​
8.25E+00​
2.26E+01​
8.25​
0.00​
8.35E+00​
2.25E+01​
8.35​
0.00​
8.45E+00​
2.25E+01​
8.45​
0.00​
8.55E+00​
2.27E+01​
8.55​
0.00​
8.65E+00​
2.26E+01​
8.65​
0.00​
8.75E+00​
2.25E+01​
8.75​
0.00​
8.85E+00​
2.26E+01​
8.85​
0.00​
8.95E+00​
2.27E+01​
8.95​
0.00​
9.05E+00​
2.26E+01​
9.05​
0.00​
9.15E+00​
2.27E+01​
9.15​
0.00​
9.25E+00​
2.27E+01​
9.25​
0.00​
9.35E+00​
2.27E+01​
9.35​
0.00​
9.45E+00​
2.26E+01​
9.45​
0.00​
9.55E+00​
2.26E+01​
9.55​
0.00​
9.65E+00​
2.27E+01​
9.65​
0.00​
9.75E+00​
2.27E+01​
9.75​
0.00​
9.85E+00​
2.27E+01​
9.85​
0.00​
9.95E+00​
2.27E+01​
9.95​
0.00​
 
  • Informative
Likes Alex A
  • #10
So, what I've written might contain mistakes, and it's simplified and not exactly what you asked for. I've added an energy bin tally between 4.4 and 4.8 MeV. The peak corresponds to a stopping power of around 34 MeV/mm. I don't think X has the capability to plot energy loss versus true distance.

I found some fairly old tables here and Chromium is missing, so I tried the numbers for Vanadium and got a result of 33.7 MeV/mm. I'm pleased, if slightly weirded out by the match. It seems a bit too good to be true. I don't know why your numbers are 2/3rds of this. I hope the attached output is of some help.
 

Attachments

  • outl.txt
    22.2 KB · Views: 102
  • Like
Likes emilmammadzada
  • #11
Sorry, I did the experiment for germanium in geant4. That's why our data do not match.
 
  • Haha
Likes Alex A
  • #12
emilmammadzada said:
Sorry, I did the experiment for germanium in geant4. That's why our data do not match.
Alex A said:
So, what I've written might contain mistakes, and it's simplified and not exactly what you asked for. I've added an energy bin tally between 4.4 and 4.8 MeV. The peak corresponds to a stopping power of around 34 MeV/mm. I don't think X has the capability to plot energy loss versus true distance.

I found some fairly old tables here and Chromium is missing, so I tried the numbers for Vanadium and got a result of 33.7 MeV/mm. I'm pleased, if slightly weirded out by the match. It seems a bit too good to be true. I don't know why your numbers are 2/3rds of this. I hope the attached output is of some help.
Canvas.png

Depth(um)​
Energy loss​
Depth(um)​
(Atoms/cm^3)/(Atoms/cm^2)​
0.05​
34.50​
0.05​
0.00​
0.15​
34.50​
0.15​
0.00​
0.25​
34.56​
0.25​
0.00​
0.35​
34.60​
0.35​
0.00​
0.45​
34.52​
0.45​
0.00​
0.55​
34.63​
0.55​
0.00​
0.65​
34.52​
0.65​
0.00​
0.75​
34.65​
0.75​
0.00​
0.85​
34.67​
0.85​
0.00​
0.95​
34.58​
0.95​
0.00​
1.05​
34.70​
1.05​
0.00​
1.15​
34.64​
1.15​
0.00​
1.25​
34.66​
1.25​
0.00​
1.35​
34.85​
1.35​
0.00​
1.45​
34.68​
1.45​
0.00​
1.55​
34.80​
1.55​
0.00​
1.65​
34.83​
1.65​
0.00​
1.75​
34.82​
1.75​
0.00​
1.85​
34.83​
1.85​
0.00​
1.95​
34.98​
1.95​
0.00​
2.05​
34.82​
2.05​
0.00​
2.15​
34.94​
2.15​
0.00​
2.25​
34.88​
2.25​
0.00​
2.35​
34.83​
2.35​
0.00​
2.45​
34.83​
2.45​
0.00​
2.55​
34.89​
2.55​
0.00​
2.65​
35.10​
2.65​
0.00​
2.75​
35.01​
2.75​
0.00​
2.85​
35.05​
2.85​
0.00​
2.95​
35.09​
2.95​
0.00​
3.05​
35.01​
3.05​
0.00​
3.15​
35.04​
3.15​
0.00​
3.25​
35.02​
3.25​
0.00​
3.35​
35.13​
3.35​
0.00​
3.45​
35.09​
3.45​
0.00​
3.55​
35.10​
3.55​
0.00​
3.65​
35.20​
3.65​
0.00​
3.75​
35.25​
3.75​
0.00​
3.85​
35.29​
3.85​
0.00​
3.95​
35.16​
3.95​
0.00​
4.05​
35.16​
4.05​
0.00​
4.15​
35.19​
4.15​
0.00​
4.25​
35.23​
4.25​
0.00​
4.35​
35.29​
4.35​
0.00​
4.45​
35.26​
4.45​
0.00​
4.55​
35.34​
4.55​
0.00​
4.65​
35.37​
4.65​
0.00​
4.75​
35.38​
4.75​
0.00​
4.85​
35.47​
4.85​
0.00​
4.95​
35.38​
4.95​
0.00​
5.05​
35.43​
5.05​
0.00​
5.15​
35.46​
5.15​
0.00​
5.25​
35.49​
5.25​
0.00​
5.35​
35.41​
5.35​
0.00​
5.45​
35.57​
5.45​
0.00​
5.55​
35.39​
5.55​
0.00​
5.65​
35.64​
5.65​
0.00​
5.75​
35.59​
5.75​
0.00​
5.85​
35.59​
5.85​
0.00​
5.95​
35.57​
5.95​
0.00​
6.05​
35.58​
6.05​
0.00​
6.15​
35.60​
6.15​
0.00​
6.25​
35.58​
6.25​
0.00​
6.35​
35.69​
6.35​
0.00​
6.45​
35.63​
6.45​
0.00​
6.55​
35.68​
6.55​
0.00​
6.65​
35.70​
6.65​
0.00​
6.75​
35.85​
6.75​
0.00​
6.85​
35.83​
6.85​
0.00​
6.95​
35.67​
6.95​
0.00​
7.05​
35.84​
7.05​
0.00​
7.15​
35.83​
7.15​
0.00​
7.25​
35.91​
7.25​
0.00​
7.35​
35.70​
7.35​
0.00​
7.45​
35.92​
7.45​
0.00​
7.55​
35.94​
7.55​
0.00​
7.65​
36.01​
7.65​
0.00​
7.75​
36.07​
7.75​
0.00​
7.85​
35.90​
7.85​
0.00​
7.95​
35.96​
7.95​
0.00​
8.05​
35.89​
8.05​
0.00​
8.15​
35.99​
8.15​
0.00​
8.25​
36.05​
8.25​
0.00​
8.35​
36.05​
8.35​
0.00​
8.45​
36.04​
8.45​
0.00​
8.55​
36.15​
8.55​
0.00​
8.65​
36.17​
8.65​
0.00​
8.75​
36.11​
8.75​
0.00​
8.85​
36.18​
8.85​
0.00​
8.95​
36.10​
8.95​
0.00​
9.05​
36.25​
9.05​
0.00​
9.15​
36.25​
9.15​
0.00​
9.25​
36.28​
9.25​
0.00​
9.35​
36.28​
9.35​
0.00​
9.45​
36.28​
9.45​
0.00​
9.55​
36.32​
9.55​
0.00​
9.65​
36.40​
9.65​
0.00​
9.75​
36.27​
9.75​
0.00​
9.85​
36.41​
9.85​
0.00​
9.95​
36.43​
9.95​
0.00​
For Cromium 5MeV proton transporting results .Thickness 10 um ,YZ parameters 1 mm
 
  • Like
Likes Alex A

FAQ: Particles transporting in MCNP5

What is MCNP5?

MCNP5 is a Monte Carlo N-Particle transport code that is used to simulate the transport of particles through a given material or geometry. It is widely used in nuclear engineering, medical physics, and other fields to study the interaction of particles with matter.

How does MCNP5 simulate particle transport?

MCNP5 uses the Monte Carlo method to simulate the transport of particles. This involves randomly sampling the physical processes that occur when a particle interacts with matter, such as scattering, absorption, and production of secondary particles. The code then tracks the particles through the material or geometry, building up statistical results over many simulations.

What types of particles can be transported in MCNP5?

MCNP5 can simulate the transport of neutrons, photons, electrons, and other particles. It also has the capability to simulate the transport of multiple types of particles simultaneously, making it a versatile tool for many applications.

What are some common uses of MCNP5?

MCNP5 has a wide range of applications, including nuclear reactor design and analysis, radiation shielding design, medical imaging and therapy, and nuclear waste management. It is also commonly used in research and development for new technologies and materials.

What are the advantages of using MCNP5 for particle transport simulations?

One of the main advantages of using MCNP5 is its ability to simulate complex geometries and materials with high accuracy. It also has a user-friendly interface and a large user community, making it a widely used and well-supported tool. Additionally, MCNP5 allows for detailed analysis of particle interactions, making it a valuable tool for understanding and optimizing particle transport processes.

Back
Top