Recent content by Hamidul

Hello @Alex

Hi Hi Alex, The spectrometer result is below. Here I am using a Nested Neutron Spectrometer. Here it measures neutron fluence (n/(cm^2*s). The data are taken for a bare Californium-252 neutron source at a distance of 100cm from the source. Yes, the data are unfolded with the aid of the...

In MCNP, the flux value (f2 or f4 tally) comes with the flux per neutron. But in the practical spectrometer, the unit is different. How can I convert MCNP data that matches my spectrometer-generated data? When I go to plot both datasets, the units are different. However, my source emission rate...

Thank you so much

One more query, please suggest me a Watt energy spectrum for Am-Be neutron source. I have another code with Am-Be with same geometry. My existing function is -3 0.933020 3.46195 for Am-Be

That is awesome. This results agrees with my calculated ambient dose equivalent( actually free field dose equivalent ). though the values are little bit smaller than the calculated FFDE. I do not know how to interpret this. In addition , I have also measured FFDE with survey meter, the values...

If I do so, I will get dose against various energy. Right? But, I need also measure the dose at various distances like 30cm, 40cm,... 100cm from the source? For getting that which tally should I use? F6? the results in my input file is huge.

Hello Alex, are you here? I want to measure the dose rate in my same simulation geometry surface. I did also write a code for that, got a single data. But I am struggling to interpret my data, I need to convert it dose rate microsievert per hour.

Thanks a lot Alex, By following your instruction I was able to find out all of my spectra which matched with my real result beautifully. Without your and others help in this forum, may be I would not been able to finish that. Long live the PHYSICSFORUM. Sorry for late update.

Thank you Alex, I will keep updating my outcomes.

Hello ALEX , here are my both results,

Hello Alex, I uploaded both the file, but due to some issues of the network it did not worked. Yes, I used NNS (Nested Neutron Spectrometer) to get my results. My professor said that my experimental results are good and I have to simulate the same things to get a spectra. Moreover, should...

Hello everyone , in my mcnp coding for finding neutron spectroscopy I used F2 tally across a surface. Is it correct or I should use f4 tally? Morever I need to transform the flux data into neutron fluence. How can I do that. Here I uploaded my code. Though my data from codes is way more...

I modified the output as of your code SDEF erg=d1 SP1 -3 1.025 2.926 the output file and the corresponding exel graph is uploaded below

Sometimes the name of your input file create problems, do not put any space in your input file . such as you can write mcnpcode.txt but you cannot write mcnp code.txt .. The input file that you run dislikes any space between it. And try to make your input file as short as possible. I am a...