Recent content by Salman Khan

How to check the the saturation limit of electron yield by gamma photon incident on a metal sheet using mcnp. As I know that mcnp give result per Particle , but how can I check the final saturation limit of that metal. Is it possible to check it for different numbers from 10e6 to 10 e12 to see...

How does it possible to draw complex geometry in Mcnp?. If the only solution is to import cad drawing into visual editor in this case, please explain, is there any tutorial link to do it . Thanks is advance

Thanks Alex

I am interested to simulate a problem in mcnp6, in which gamma rays (energy let say 10 Mev) incident on a aluminum disk and produce electron spectrum which further move in a gas (e.g co2)cell to produce chernkove radiation. Here gamma produce electron and electron further produce chernekov, in...

Yes you are right I can decrease distance to further improve results. But what will I do if distance of source and detector is 30 cm in an experimental setup, here the only choice seem to me is to convert point isotropic source to a conical source.

I just want to model my problem more efficiently by entering more possible particles to the tally region to reduce statistical error. As we know mcnp gives answer per particle that is why I want to enter more particle to the region of interest so that I can get more accurate result. M I right...

When I simulate a point isotropic gamma source in mcnp usually number of particle histories to the tally region (let say a detector placed at 30 cm from point source) is much low (few hundreds only) as compared to actually particle histories (1.0E7), Will it be correct if convert isotropic...

F8 tally is pulse height tally use in MCNP. Is it possible to see pulse height vs. time response in MCNP (as we can see on the oscilloscope) of, say, a scintillator detector placed in front of a pulsed X-ray source?

@DamienA thanks a lot dear

Basically I want to find the electron yield of Au-79 by incident gamma photon of energy 2 Mev using point gamma source. Here if I use mode p e and if i use tallis F11:p (incident photon on front plate of AU-79) and F21:e (emitted electron by Au-79 due to incident photon). Yield=F21:e/F11:p. My...

I am interested to find the electron yield of a material like Aluminium by incident photon of energy let say 2 Me. I used Mode p e And tally F11: e accros desired surface F21: p across desired surface only to find its value. Is it necessary to use phy card as well or no need of it. Thanks in...

Thanks Alex, I just want to see that this low energy photon will either reach or not to a region of interest I just want to see their transport

Hi everyone. is it possible to simulate low energy photon in wavelength range (300 nm to 1000 nm) in MCNP. If not possible in mcnp please suggest any other code to simulate it. thanks

Ok thanks

I know to convert F6 tally (Mev/g) to dose (Gray) but how to find dose rate i.e Gray/hour from MCNP ?