Evaluations of fission product capture cross sections for ENDF/B-V
Capture cross section evaluations were made for the 36 most important fission product absorbers in a fast reactor system. These evaluations were obtained by use of a generalized least-squares approach with calculations being performed with the computer code FERRET. These results will provide the major revisions to the ENDF/B-IV Fission Product Cross Section File which will be released as part of ENDF/B-V. Input for the cross section adjustment calculations included 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, and 4000. Comparisons of these evaluations with recent capture measurements are presented. 14 figures.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- EY-76-C-14-2170
- OSTI ID:
- 5629544
- Report Number(s):
- HEDL-SA-1907; CONF-791058-42
- Country of Publication:
- United States
- Language:
- English
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A=90-149
Experimental-- Nuclear Reactions & Scattering-- (-1987)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BARYON REACTIONS
BARYONS
CAPTURE
DATA
DATA FORMS
ELEMENTARY PARTICLES
ENERGY RANGE
EV RANGE
EVALUATED DATA
FAST NEUTRONS
FERMIONS
FISSION PRODUCTS
GRAPHS
HADRON REACTIONS
HADRONS
INFORMATION
INTERMEDIATE NEUTRONS
ISOTOPES
KEV RANGE
LEAST SQUARE FIT
MAXIMUM-LIKELIHOOD FIT
NEUTRON REACTIONS
NEUTRONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUCLEONS
NUMERICAL DATA
NUMERICAL SOLUTION
RADIOACTIVE MATERIALS