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Posted: Wed May 12, 2021 2:50 pm
If I want to calculate the neutron flux distribution of each rod in the entire reactor, or the distribution of a specific rod, how to achieve it，just like the syntax 'set cpd' to get the power distribution of each fuel rod ,thank you:(
Posted: Wed May 12, 2021 3:07 pm
Use the detector card, see ‘det
’, to define the detector/tally that represents the estimate you are looking for.
Additional information and examples can be found in the Serpent 1 manual
(Section 7.1) and/or the Tutorial
and/or the Collection of example input files
Posted: Wed May 12, 2021 3:37 pm
I know how to use 'dl' to calculate the flux of the fuel assembly grid, but because there are fuel rod grid divisions in the assembly, I don’t know how to calculate the flux of each fuel rod in the assembly, do I need to use "dl" to calculate twice ?
Posted: Wed May 12, 2021 3:49 pm
Instead of a lattice detector, 'dl
', you could use mesh-detectors (super-imposed collision detectors): e.g. 'dx
' (Cartesian), 'dh
' (hexagonal) or, 'dn
Note: the spatial integration domain for each detector needs to be specified: e.g., if you use mesh detectors, you could define a pin-level mesh-detector, an assembly-level mesh-detector and/or full-core mesh-detector. Nonetheless, you could always do some post-processing on the detectors' estimates.
Posted: Wed May 12, 2021 3:55 pm
I seem to understand what you mean, thank you very much