Recent content by Mingzhu

Thank you very much for sharing!I have a rough idea of where the issue in my code might be, and I'll thoroughly check it. At the same time, I have another question. I want to calculate the energy spectrum for photons and neutrons using an MCNP input file. Could you help me to check the...

Thank you very much. This indicates that there is no issue with the simulation code, but there might be an error in the processing code. I exported tally8/tally28 to a txt file and used the above code for processing. I'm unsure where the problem lies. Could you please share your code or any...

yes,this is alpha and I have also processed protons, but they do not match.I have placed the output file in the attachment. Thank you very much!

Thank you very much for your guidance. it has been immensely helpful to me.The gas density is 0.000185,I writen wrong. now I change it to 7.77e-5.However, I noticed a small difference. When plotting the yfy/ydy graphs for alpha particles based on my previous code, I observed that the y-ydy plot...

yes,I have placed the input file in the attachment.

Thank you very much for your patient explanation. I believe I have a clearer understanding of microdosimetry in MCNP now. However, when it comes to calculating alpha particles, I excluded heavy ions from the simulation. I obtained a record of alpha counts, and I wonder if this approach is...

Thank you very much! I am a bit confused about how to apply the F6 and F8 tally types in MCNP to calculate lineal energy. I understand that the F6 Tally can be used to obtain the total deposited energy for each track during the simulation, while the F8 Tally outputs pulse height information for...

the code file is attached