Published October 1992 | Version v1
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Evaluation of neutron nuclear data for 249Cf

  • 1. Chinese Nuclear Data Center, Beijing, BJ (China)

Description

A complete set of neutron nuclear data from 10-5 eV to 20 MeV in ENDF/B-6 format has been evaluated for 249Cf based on measured data, systematics predications and model theory calculations. The evaluated quantities are the total, elastic and inelastic scattering, fission, capture, (n,2n), (n,3n) reaction cross sections, the resolved and unresolved resonance parameters, the angular and energy distributions of emitted neutrons and the average number of neutrons emitted per fission. The numerical data are available in ENDF/B-6 format

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Part of:
Communication of nuclear data progress: No.6 Supplement (1992)

Additional details

Publishing Information

ISBN
7-5022-0646-9
Imprint Title
Communication of nuclear data progress: No.6 Supplement (1992)
Imprint Pagination
125 p.
Journal Page Range
p. 118-123.
Report number
CNIC--00690

Optional Information

Secondary number(s)
CNDC--0010; INDC(CPR)--028/L.