INEL integral data-testing report for ENDF/B-V fission-product and actinide cross sections

Technical Report · Wed Apr 01 04:00:00 EST 1981

DOI:https://doi.org/10.2172/6418860· OSTI ID:6418860

Anderl, R. A.

An integral-testing study done at the Idaho National Engineering Laboratory for ENDF/B-V fission-product and actinide cross sections is presented. The integral data base used comprises 52 measured spectrum-averaged cross sections for 34 fission-product neutron capture reactions and for 7 higher actinide fission and capture reactions. Included in this data base are integral data from both CFRMF and EBR-II irradiations. Neutron spectra for the irradiation fields are specified and characterized. For the CFRMF related data testing, multigroup flux representations based on transport calculations with both ENDF/B-IV and ENDF/B-V cross sections were used in the calculation of spectrum-averaged cross sections. Neutron spectra used for the EBR-II related data testing are based on multigroup flux representations obtained from spectrum-unfolding analyses. Calculated spectrum-averaged cross sections for the fission products and actinides were obtained using both ENDF/B-IV and ENDF/B-V data. Where possible, calculations were made to estimate the uncertainty in the calculated spectrum-averaged cross sections because of uncertainties and correlations in the input fluxes. Sources of discrepancies in integral testing were examined. These included inaccuracies due to changes in the spectrum shape and the use of incorrect weighting functions for the generation of collapsed cross sections. The results of this study indicate that the changes made in the fission-product and actinide cross sections in going from ENDF/B-IV to ENDF/B-V resulted in more consistency for 28 of the integral data, less consistency for 14 of the integral data and no change for 9 of the integral data.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6418860
• Report Number(s): EGG-PHYS-5406
• Country of Publication: United States
• Language: English

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73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ACTINIDE ISOTOPES
BARYON REACTIONS
BREEDER REACTORS
CAPTURE
CFRMF REACTOR
CROSS SECTIONS
DATA
DATA PROCESSING
EBR-2 REACTOR
EPITHERMAL REACTORS
EXCITATION FUNCTIONS
EXPERIMENTAL DATA
EXPERIMENTAL REACTORS
FAST FISSION
FAST REACTORS
FBR TYPE REACTORS
FISSION
FISSION PRODUCTS
FUNCTIONS
GRAPHS
HADRON REACTIONS
INFORMATION
INTEGRAL CROSS SECTIONS
ISOTOPES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
NEUTRON FLUX
NEUTRON REACTIONS
NEUTRON SPECTRA
NUCLEAR DATA COLLECTIONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL DATA
POWER REACTORS
PROCESSING
RADIATION FLUX
RADIOACTIVE MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
SPECTRA
SPECTRA UNFOLDING
ZERO POWER REACTORS