Published April 1975 | Version v1
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Neutron cross section tabulated data

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Description

Evaluations of cross sections for the reactions 235U(n,f), 238U(n,f), 238U(n,γ), 237Np(n,f), and 239Pu(n,f) are given

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Publishing Information

Imprint Title
ENDF/B-IV dosimetry file
Imprint Pagination
p. 207-285.
Report number
BNL-NCS--50446