MCNPX - problem in cross-section

In summary, the conversation is discussing the use of MCNPX to calculate the effects of radiation on breast tissue. The person is trying to collimate the beam of radiation by using a lead shield, but when they cut the breast in half, the collimation stops working. This is due to the diffusion of radiation in the breast tissue. The person is seeking help in understanding how to properly account for this diffusion in their calculations.
  • #1
Alexander Camargo
19
2
Why does mcnpx not recognize the shell when I crop the cell in half? I put on a lead shield. I put everything (covering everything) and it worked. I cut half and the shield stop of work, but the cell is there.
upload_2019-1-21_13-8-4.png


10 2 -0.9500 (-1 2 -3) #20 imp:p=1 VOL=149.2256511 $ espessura / thickness
20 1 -0.964 (-5 6 -7) imp:p=1 VOL=353.4291735 $ mama / breast
30 3 -0.001205 (-9 -10 11) (1 : -2 : 3 : 5 : -6 : 7) imp:p=1 VOL=20.1061930 $ ar / air
40 4 -11.35 (-12 13 -14 -15) imp:p=1 $ chumbo / Lead
C ----- Acompanhamento -----
80 3 -0.001205 (-80) #10 #20 #30 #40 imp:p=1 $ Mundo-Interno / universe
90 0 (80) imp:p=0 $ Fim do Acompanhamento

C -------------Geometrias / geometries ----------------
C ------------ espessura / thickness ----------
1 cz 8
2 pz -2.5
3 pz 2.5
C ------------ mama / breast -------------
5 cz 7.5
6 pz -2
7 pz 2
C ------------ AR / air -------------
9 cz 8
10 pz 2.7
11 pz 2.5
C ------------ Lead --------
12 cz 8
13 pz 2.75
14 pz 3.75
15 px 0
C --- Fim de Acompanhamento / universe ---
80 SO 225 $ Mundo

area 0 100.53 100.53 0 88.35 88.35 0 100.53 100.53 100.53 0 0 0
mode P $ fotons / photons
C
C -------------- Monoenergetic - conic source ----------------
sc1 raio x monoenergetico para mamografia
SDEF POS=0 0 60 ERG=0.018 PAR=2 VEC=0 0 -1 DIR=d1
SI1 -1 0.991227901 1 $ histogram for cosine bin limits
SP1 0 0.99561395 0.00438605 $ frac. solid angle for each bin
SB1 0 0 1 $ source bias for each bin
 

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  • #2
Hi,
if I understand your case "complete" you have 1 cm of lead between your source and your calculation cell. For 18 keV photon you have Something like exp(-1000) of attenuation (sorry the NIST site is closed and I don't have the attenuation factor) : It is impossible to have a photon in breast!
In "half" case I think you have diffusion in breast,
 
  • #3
PSRB191921 said:
Hi,
if I understand your case "complete" you have 1 cm of lead between your source and your calculation cell. For 18 keV photon you have Something like exp(-1000) of attenuation (sorry the NIST site is closed and I don't have the attenuation factor) : It is impossible to have a photon in breast!
In "half" case I think you have diffusion in breast,
Thanks for help.

my idea is to close half of the breast to collimate the beam of conical radiation. but it only colimate when put complete lead. when cut de half, he stop the colimation.

What would be diffusion in the breast?
 

1. What is MCNPX and what is its purpose?

MCNPX is a Monte Carlo N-Particle transport code designed for simulating and analyzing the transport of particles through matter. It is used in a wide range of applications, including nuclear engineering, medical physics, and radiation protection.

2. What does "problem in cross-section" mean in the context of MCNPX?

"Problem in cross-section" refers to an issue that arises when trying to accurately model the behavior of particles in a material due to incorrect or missing data in the cross-section libraries used by MCNPX. Cross-section data is essential for determining the probability of a particle interacting with a material, and any errors in these values can lead to inaccurate results.

3. How can I troubleshoot and fix cross-section problems in MCNPX?

There are several steps you can take to troubleshoot and fix cross-section problems in MCNPX. These include checking for updates to the cross-section libraries, verifying the input data and parameters used in the simulation, and adjusting the settings for the simulation to improve accuracy.

4. Are there any common causes of cross-section problems in MCNPX?

Yes, there are several common causes of cross-section problems in MCNPX. These include using outdated cross-section libraries, incorrect input data or parameters, and inadequate simulation settings. Additionally, complex geometries and materials can also contribute to cross-section problems.

5. How important is it to address cross-section problems in MCNPX simulations?

It is crucial to address cross-section problems in MCNPX simulations as they can significantly impact the accuracy and reliability of the results. Inaccurate cross-section data can lead to incorrect conclusions and potentially dangerous situations, especially in applications related to nuclear engineering and radiation protection.

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