Published June 2000 | Version v1
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Evaluation of n + 144,148,154Sm reaction data

  • 1. China Nuclear Data Center, CIAE, Beijing (China)

Description

The neutron cross section data were evaluated for n + 144,148,154Sm reaction in the energy range 10-5 eV to 20 MeV. Spline function was used in the experimental data fit calculation. The corresponding JENDL-3 data are accepted in the energy range of 0.025 to 100 Kev. The comparisons among calculation data and experimental data, JENDL-3 data ENDF/B-6 data are presented

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Part of:
Communication of nuclear data progress No. 23 (2000)

Additional details

Publishing Information

ISBN
7-5022-2202-2
Imprint Title
Communication of nuclear data progress No. 23 (2000)
Imprint Pagination
165 p.
Journal Page Range
p. 129-132
Report number
CNIC--01475

Optional Information

Notes
1 tab., 2 figs., 6 refs.
Secondary number(s)
CNDC--0027; INDC(CPR)--050/L