|Message: Re: Cf 252 Neutron Source||Not Logged In (login)|
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I'm doing simulations of a Cf252 using a similar macro like the txt file, however, I want to simulate 4 n in each evt(~number of n emitted per fission), so I use the option /gps/source/add 1, the problem is that then, when I analyze the results, I always have 2 delayed evts when I expect at least in some cases 4(time of n captures different) I dont know if there is necessary some others specifications in the macro file(attached in a txt file).
I am interested in study the n captures and the gamma emitted on these captures in different materials...Actually I already have this information with the actual macro, but I want to use these gammas from n captures to calibrate my detector and to do that is necessary have the delayed evts separately...
Thanks in advance,