An old IEC standard (International Electrotechnical Commission) has proposed a maximum neutron dose limit in the patient plane of 0.5 mGy of neutrons per Gy of x-ray. I don't know if this is still relevant.
In addition in term of energy, you have a large number of photonuclear reaction...
Hi,
To calculate a spectrum in Ge, the tally F8 is the right tally.
In the MCNP pack I don't think there is a proton library for B-11, so a model is applied (you can look in your xsdir or your output file). I don't know if this is the problem but you should try installing a p-B11 library to try.
Hi,
The your result is logical. 1E-5 is in MeV/cm i.e. 100 keV/µm but for electrons the LET is much lower than this value: all results are in the bin 0 - 1E-5 therefore also between 0 and 1e-3.
you should sample between 0 and less than 10 keV/µm
with F5:n x y z .1 you calculate the fluence at the coordinate (x,y,z). With DE/DF the fluence is transformed into equivalent dose.
In my input file I put :
F5:n 0 0 10 .1 for a distance of 10 cm from the source
F15:n 0 0 50 .1 for a distance of 50 cm from the source
F25:n 0 0 100 .1 for a...
your dose calculation is strange, because:
- you do the calculation through a sphere while the notion of dose is punctual. In principle with mcnp we calculate the fluence at a point (for example with a type 5 tally) and we apply a DE/DF to it.
- Cf-252 is a spectrum not monoenergetic at 2.26 MeV...
I don't know your processing code, can you give your output file I will try with my processing code (Excel :-))
I think your curve is for alpha, can your try with protons and alpha+ protons ?