|Message: Question about Geant4 absorbed dose equation||Not Logged In (login)|
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Dear Geant4 users,
I am a user who are new to Geant4.
I simulate neutron detection using Geant4.
In the course of data acquisition, I have two questions.
I want to know that neutron detected is converted to absorbed dose using what formula.
To calculate the absorbed dose, MCNP use F4 tally and Dose Energy and Function Cards.
The equation used in the Dose Energy and Function Cards and F4 tally is the same as the attached.
Is it possible to know the formula as described above is used in any form in Geant4?
Is there a formula of all stochastic calculations that occurs to neutron detection from neutron generator?
I want to know if any.
if you know about two of the above, please tell me
Attachment: http://hypernews.slac.stanford.edu/HyperNews/geant4/get/AUX/2014/07/16/22.27-4035-1.png http://hypernews.slac.stanford.edu/HyperNews/geant4/get/AUX/2014/07/16/22.27-28284-2.png