|Message: How to multiply the flux by a specific cross section ?||Not Logged In (login)|
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I want to simulate the response of a He3 detector, embeded in a polyethylene moderator, to a flux of neutrons. Because of the low density of He3, the actual He3(n,p) events will be very rare in a simulation (I guess). Therefore I want to:
1. calculate the neutron flux in the detector volume as a function of energy (over some 9-10 decades). I found that this can be done, quite tediously, with a regular flux scorer + ParticleFilterWithKineticEnergy (or something like that) for every energy bin requested. I want 200 , 20 per decade.
2. multiply the calculated flux, at the end of the run, by the He3(n,p) cross section, as a function of energy.
THe question is: How can I get the He3(n,p) cross section values, at the end of the run ?