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Jeremy
Apr 16, 2018, 12:02:02 PM4/16/18
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I am using TRITON version SCALE 6.1.3 to generate burnup dependent neutron cross-section libraries for Candu fuel bundles, saving the ft33f001* files for subsequent use with ORIGEN. I can obtain the burnup boundaries for the budle average library using a simple hand calculation, or from the TRITON output under "Library Burnup". My question is how can I obtain the burnup boundaries for the ring specific libraries (ft33f001.mix0001, ft33f001.mix002 etc)
Jeremy
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