Recent content by PSRB191921

Hi, you are trying to calculate an F5 (and F15) at (0,0,0) where your neutrons are emitted. Try to remove this calculation point, like this : F5:N 10 0 0 1 20 0 0 1 30 0 0 1 40 0 0 1 50 0 0 1 60 0 0 1 70 0 0 1 80 0 0 1 90 0 0 1 100 0 0 1...

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.

oups you are right !

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

Am-Be is not a fission source, so it is not a watt spectrum. You must input the spectrum by bin.

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...

this is my Excel file

with your file and my processing it gives: not so bad! Some convergence problem (with more nps it will be ok)

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 ?

you must change your importance (you have imp:n,e=1) put in block 3 : imp:n 1 1 1 0 imp:h,a 1 1 0 0 The 7th parameter of the “phys:n” card and “phys:p” is set to 1 to ensure the generation and transport of recoil and (n,p) protons as well as recoil heavy ions : PHYS:N 20 20 0 J J J 1 -1 J J J 0...

can you give your mcnp input file ?

The lineal energy distribution for each secondary heavy charged particle is estimated using a F6 tally type for energy deposit coupled to a pulse height tally F8 for each heavy charged particle specie. An anticoincidence pulse height card, i.e., “ft8 phl”, is added to the F8 tally for counting...

Hi, For a TEPC irradiated with neutrons you must calculated the energy deposition of all secondary charged particules: protons, alpha, heavy ions and possibly deuterons, tritons. Electrons and photons can be neglected. For neutrons of 14 MeV a lineal energy of 10 keV/µm gives the maximum of the...

I would have used a F4:n 6