ENDF/B-5 fission product cross section evaluations

Technical Report · Sat Dec 01 04:00:00 EST 1979

DOI:https://doi.org/10.2172/5724647· OSTI ID:5724647

Schenter, R. E.; England, T. R.

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.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: EY-76-C-14-2170
• OSTI ID: 5724647
• Report Number(s): HEDL-SA-1969-FP; CONF-791223-3
• Country of Publication: United States
• Language: English

Related Subjects

651725* -- Nuclear Properties & Reactions
A=90-149
Experimental-- Nuclear Reactions & Scattering-- (-1987)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BARYON REACTIONS
BARYONS
BURNUP
CAPTURE
CROSS SECTIONS
DATA
DATA FORMS
ELEMENTARY PARTICLES
EVALUATED DATA
FAST NEUTRONS
FERMIONS
FISSION PRODUCTS
GRAPHS
HADRON REACTIONS
HADRONS
INFORMATION
INTEGRALS
ISOTOPES
LEAST SQUARE FIT
MAXIMUM-LIKELIHOOD FIT
NEUTRON REACTIONS
NEUTRONS
NUCLEAR DATA COLLECTIONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUCLEONS
NUMERICAL DATA
NUMERICAL SOLUTION
RADIOACTIVE MATERIALS
RESONANCE INTEGRALS
TABLES
THERMAL NEUTRONS