Evaluation of neutron cross sections for /sup 244/Cm, /sup 246/Cm, and /sup 248/Cm
- 1 January 1977
- report
- Published by Office of Scientific and Technical Information (OSTI)
Abstract
An evaluation of neutron cross sections for /sup 244/ /sup 246/ /sup 248/Cm using the ENDF/B format is presented. Primary data input included differential measurements, integral measurements, nuclear model calculations, and reactor production experience. (SDF)Keywords
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