Proton transport problem using MCNP

Click For Summary
SUMMARY

The forum discussion centers on issues related to proton transport using MCNP6 and MCNPX, specifically the unexpected loss of protons due to energy cutoff and the lack of secondary particle production during interactions. Users highlighted that MCNP6.1 does not support delta-ray production from charged particles, a feature introduced in MCNP6.2. Participants shared resources, including a thesis on proton therapy and suggested searching for terms like "MCNP proton slowing down" to gain further insights into the physics involved.

PREREQUISITES
  • Familiarity with MCNP6 and MCNPX simulation software
  • Understanding of charged particle transport and ionization processes
  • Knowledge of energy cutoff parameters in particle simulations
  • Basic concepts of delta-ray production in charged particle interactions
NEXT STEPS
  • Research the differences between MCNP6.1 and MCNP6.2 regarding delta-ray production
  • Explore the continuous slowing down approximation in proton transport
  • Investigate how to integrate PIXE cross-section libraries with MCNP
  • Examine the thesis "Using MCNPX to Calculate Primary and Secondary Dose in Proton Therapy" for relevant methodologies
USEFUL FOR

This discussion is beneficial for medical physicists, researchers in proton therapy, and simulation specialists working with MCNP software who are troubleshooting proton transport issues.

Antonio_A
Messages
3
Reaction score
3
Hello everyone !

I wanted to ask you if anyone ever encountered problems with proton transport using MCNP. In particular, the production of electrons when protons interact with matter. I have been trying to figure it out modifying the different physics cards (phys, lca, ...) with no result. Since a proton is a charged particle, ionization is expected and not even a single secondary particle is created while, in the output file most (if not all) of the incident protons are lost by energy cutoff meaning that they lose energy.
If anyone with experience in proton transport could enlighten me or give me some clues, it would be great.

Thanks,
Antonio
 
  • Like
Likes evjanuclear
Engineering news on Phys.org
Thanks for the thread! What version of MCNP is one using, MCNPX or MCNP6?
 
Last edited by a moderator:
From - https://mcnp.lanl.gov/pdf_files/la-ur-13-22934.pdf
it states, "Transport with elastic and inelastic nuclear scattering, Continuous slowing down approximation, energy and angle straggling, magnetic field effects"

There may be some insight in this thesis - Using MCNPX to Calculate Primary and Secondary Dose in Proton Therapy
https://smartech.gatech.edu/bitstream/handle/1853/39499/ryckman_jeffrey_m_201105_mast.pdf

One could search on "MCNP proton slowing down" or "continuous slowing down approximation" with or without MCNP

I have a colleague who has used MCNPX and MCNP6 to simulate the effects of proton beam on targets.
 
  • Like
Likes evjanuclear
Thanks for your replies

Greg Bernhardt said:
What version of MCNP is one using, MCNPX or MCNP6?

MCNP 6

Astronuc said:
There may be some insight in this thesis

I already have looked into it, it describes well how to setup the physics transport of protons in the input file but it treats a completely different case and it is useless in my situation as i described the most complete case for protons.I have found PIXE (particle-induced x-ray emission) cross-section libraries. This is not a PIXE problem but since it treats the ionization as main process and it is also what i am interested in, i taught that i might as well have a look at it. Now, i don't know how to make these libraries work with mcnp and if anyone (you know) has already tried this, i would love to know how you did it.

Thanks,
Antonio
 
  • Like
Likes evjanuclear
I finally have an answer. For those wondering, MCNP6.1 is not able to compute this kind of cases. Delta-ray production from charged particles is implemented in MCNP6.2 which will be available by the end of this month.

Topic can be closed.
 
  • Like
Likes evjanuclear
Hi, I have a similar problem.I'm simulating in MCNP6 the reaction of proton beam on targets but in the simulation the 96% of the proton are lost for energy cutoff.
I don't understand why happen that. I use a tally4 to obtain the reaction in the target, but I suppose the results are wrong because the lost of protons (if they are lost they can´t interact isn´t it?)

Any idea?

Thanks,
Eva
 
Hello, I am designing an X-ray irradiator with MCNP simulation. But I am still in confusion, whether my X-ray housing will be a box or a cylinder. If the box (macrobody identifier of MCNP) is required, I am trying to match the dimension as that of the cylinder, i,e, the height will be that of the cylinder height, and the other two dimensions will be that of the radius of the cylinder (surface 52 and 53). Can anybody please help me define the surfaces? Below is my attached text file. Forgot...

Similar threads

  • · Replies 4 ·
Replies
4
Views
2K
  • · Replies 8 ·
Replies
8
Views
2K
  • · Replies 13 ·
Replies
13
Views
4K
  • · Replies 1 ·
Replies
1
Views
4K
  • · Replies 2 ·
Replies
2
Views
4K
  • · Replies 7 ·
Replies
7
Views
6K
  • · Replies 9 ·
Replies
9
Views
3K
  • · Replies 8 ·
Replies
8
Views
817
  • · Replies 17 ·
Replies
17
Views
6K
  • · Replies 2 ·
Replies
2
Views
3K