Hello.
I have a souce of neutrons and my F4 tally value (non-normalized) in a cell is 10^3/(cm^2). I want to increase the value, for exemple 10^9 /(cm^2), without modifying the area. I used FM card, but I don't want to just multiply by a scalar value. How can I increase the flux (F4 tally)?
If anyone can help, I appreciate it
Hi Otto, I am not sure I fully understand the question. Do you need to increase the value of the tally in terms of statistics? i.e. decreasing the error? Or you only want to re-normalize the result from being "per source particle" to something else? e.g. per Bq? As you've stated this is done with the FM card.
However, if you are looking to decrease the error without increasing the number of histories, then you may try tally F5 or take a look at variance reduction techniques.
I hope this helps.
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