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Jeremy
May 26, 2018, 9:20:51 PM5/26/18
to SCALE Users Group
Is the neutron cross-section library ft33f001.cmbined for a cylindrical CANDU fuel bundle weighted with the "total" flux printed in the TRITON (SCALE 6.1.3) output under "Cell Averaged Fluxes", or by a weighted average of the fluxes in the individual fuel rings?
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