ENDF/B-5 fission product cross section evaluations [electronic resource].
- Published:
- Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1979.
- Physical Description:
- Pages: 33 : digital, PDF file
- Additional Creators:
- United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Summary:
- Cross section evaluations were made for the 196 fission product nuclides on the ENDF/B-5 data files. Most of the evaluations involve updating the capture cross sections of the important absorbers for fast and thermal reactor systems. This included updating thermal values, resonance integrals, resonance parameter sets, and fast capture cross sections. For the fast capture results generalized least-squares calculations were made with the computer code FERRET. Input for these cross section adjustments included nuclear models calculations and both integral and differential experimental data results. The differential cross sections and their uncertainties were obtained from the CSIRS library. Integral measurement results came from CFRMF and STEK Assemblies 500, 1000, 2000, 3000, 4000. Comparisons of these evaluations with recent capture measurements are shown. 15 figures, 10 tables.
- Report Numbers:
- E 1.99:hedl-sa-1969-fp
E 1.99: conf-791223-3
conf-791223-3
hedl-sa-1969-fp - Subject(s):
- Other Subject(s):
- Fission Products
- Neutron Reactions
- Capture
- Resonance Integrals
- Burnup
- Cross Sections
- Evaluated Data
- Fast Neutrons
- Graphs
- Least Square Fit
- Nuclear Data Collections
- Tables
- Thermal Neutrons
- Baryon Reactions
- Baryons
- Data
- Data Forms
- Elementary Particles
- Fermions
- Hadron Reactions
- Hadrons
- Information
- Integrals
- Isotopes
- Maximum-Likelihood Fit
- Neutrons
- Nuclear Reactions
- Nucleon Reactions
- Nucleons
- Numerical Data
- Numerical Solution
- Radioactive Materials
- Note:
- Published through SciTech Connect.
12/01/1979.
"hedl-sa-1969-fp"
" conf-791223-3"
NEANDC specialist meeting on neutron cross sections of fission product nuclei, Bologna, Italy, 12 Dec 1979.
Schenter, R.E.; England, T.R.
Hanford Engineering Development Lab., Richland, WA (USA) - Funding Information:
- EY-76-C-14-2170
View MARC record | catkey: 14672676