Published November 2014
INDC Report
INDC(NDS)-0674
INDC-2632
INDC-NDS-0674
Documentation for WIMSD-formatted libraries based on ENDF/B-VII.1 evaluated nuclear data files with extended actinide burn-up chains and cross section data up to 2000 K for fuel materials
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indc-nds-0674.pdf
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