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NSR database version of May 6, 2024.

Search: Author = T.D.Huynh

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2014HU11      Nucl.Data Sheets 118, 476 (2014)

T.D.Huynh, C.Jouanne

Calculation of Delayed Neutron Yields for Various Libraries

NUCLEAR REACTIONS Z=90-98(n, F), E=thermal; calculated fast fission, thermal, delayed fission neutron yield. Compared to recommended/evaluated JEF-2.2, JEFF-3.1, ENDF/B-VI.4, ENDF/B-VII.0, JENDL/FP-2011 and data of Tuttle, Waldo and Benedetti.

doi: 10.1016/j.nds.2014.04.111
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