I am working on Nuclear Medicine MCNP application. I want to destroy cancerous cells with gamma rays(protons).
I am trying to create a source outside the skull and target a beam towards the it.
I have use various approach and I have noticed that there are no collisions of particle in the skull cells.
Checked it on MCNP X and i the beam does not get there.
F6 tally gives the average energy deposition in a cell. Is there a way i can get energy distribution across the cell.
N.B- My geometry is good.
Thank you.
yoou might want to post your question (with more specifics than here) to the MCNP forum
Dear Isaac;
If you did not observed any collision or output count in your results, its mean that you have a certain problem in somewhere such as geometry or beam direction etc. or tally definition. First of all, i would like to ask that; what kind of gamma ray did you send onto skul? I mean; did you considered your source as a point or beam? In both situation, it will affect the source definition.
On the other hand,F6 gives energy deposition but did you define the cell that where you want to observe energy deposition? In this case; for example, if you want to observe average flux in cell 2, then you have to define (F6:p 2)
If you can not solve your problem, you can directly send me your input file and i can check your possible errors.
Best Wishes
So I tried all source definition methods I found in different primers but when I put it on mcnp X the beam does not move towards the specified cell.
For the tally i specified it properly. But I have noticed the the F6 tally gives an average sum, i am interested in the energy distribution in the cell.
Any ideas i believe will be helpful.
- Badges
- Science topic
- Similar topics
- Medicine
- Oncology
- Cancer Research
- Cancer Biology
- Cancer Cells