I have electron source with 4.9E8 particles, and F4:n tally (size 3x3 cm^2) which gives me result 3.4E-9 n/cm^2. When I multiply 3.4E-9x4.9E8x9 the result is15,12 particles in my detector, but when I look at the the neutron activity table, there is 192 neutrons entering this cell. Is there possibility that this two numbers differ, or conversion isn't correct?
Hi, Hrvoje!
I don't understand this: "size 3x3 cm^2" - Is this the cross-sectional area of the cell in which the F4:n tally is specified?
The F4:n tally calculates the neutron flux in a cell using a track length estimator, i.e. the sum of all the neutron track lengths in the cell, divided by the cell volume. To calculate the number of neutrons entering the cell, I would use an F1:n tally over the cell boundaries and two cosine bins, to separate neutrons entering from the neutrons exiting the cell (the F1 tally counts the particles (weights) crossing a surface in any direction)
Hope this helps.
Cheers, Vladimir
Thank You Vladimir,
indeed, 3x3 cm^2 us the cross-sectional area of the cell in which the F4:n tally is specified.
I will try with F1:n detector.
BR, Hrvoje
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