Incorporation of ENDF-V neutron cross section data for...

IEEE Transactions on Nuclear Science 1989 / Dec. Vol. 36; Iss. 6

Incorporation of ENDF-V neutron cross section data for calculating neutron-induced single event upsets

Normand, E., Doherty, W.R.
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Volume:
36
Language:
english
Journal:
IEEE Transactions on Nuclear Science
DOI:
10.1109/23.45447
Date:
January, 1989
File:
PDF, 798 KB
english, 1989
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