Dear experts,
I am simulating the backscattering neutrons from the ILC beam dump in a two-step FLUKA run.
The final goal is to simulate the neutrons that travel back through the extraction line towards the interaction region.
So far, I have successfully scored the neutrons, which are escaping the beam dump in backward direction and crossing a scoring plane, in a collision tape using the mgdraw routine.
With the source routine, these neutrons then served as the primary particles of a second FLUKA simulation of the extraction line.
In the end of this extraction line, I have then another scoring plane to record the neutrons leaving the extraction line in another collision tape.
This final collision tape shall serve as input to a Geant4 simulation of the neutrons in the detector.
My confusion is now about the weights.
How can I find the absolute number of final neutrons and their distributions, when scaling it up to a full ILC beam?
I have read in an old fluka-discuss thread that the results of the second step shall be treated like this:
1. multiply the results by the total weight of the second step
2. divide the results by the total weight of the first step
And then I guess I could normalize this to the ILC bunch population.
Is this correct?
First, I need to find out how many neutrons will find their way through the extraction line from one primary ILC electron bunch being dumped.
I have been running all steps in multi-thread runs, so I get separate collision tapes as final results in the second step.
Will I get the total REAL number of neutrons leaving the extraction line by adding up all neutrons from all collision tapes, and then by applying the steps above on the total number of particles?
Thank you very much for your help.
Best regards,
Anne
--
Anne Schütz
Deutsches Elektronen Synchrotron (DESY)
FLA group, 1c/01.348,
Notkestr. 85
22607 Hamburg
Germany
email: anne.schuetz_at_desy.de
phone: +49 40-8998-1465
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Received on Wed Apr 11 2018 - 19:16:22 CEST