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Evaluation of the sup 59 Co resolved resonance region

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:5553456
; ;  [1]
  1. Oak Ridge National Lab., TN (United States)
The resonance parameters describing the low-energy neutron cross sections of {sup 59}Co are of considerable interest, not only because {sup 59}Co is used as a structural material in nuclear technology but also because the thermal capture cross section and the capture resonance integral of {sup 59}Co are widely used as standards and for dosimetry. High-resolution neutron transmission measurements through several thicknesses of {sup 59}Co were performed in 1986 by J. A. Harvey at the Oak Ridge Electron Linear Accelerator. The results of one of these measurements were used in the ENDF/B-VI evaluation of the {sup 59}Co total cross section above 100 keV, but the data were not used below 100 keV where the ENDF/B-VI cross sections are represented by resolved resonance parameters extracted from a recent compilation. The ENDF/B-VI file was used to compute the results of the transmission measurements of Harvey in the resonance region. Large discrepancies were observed between the computed and measured transmissions, indicating that the ENDF/B-VI-resolved resonance parameters are inadequate. As recommended, a comprehensive study of the resonance region is warranted. Therefore, the transmission measurements were analyzed with the SAMMY code, and new resonance parameters were obtained that are consistent with the transmission measurements. The ENDF/B-VI resolved resonance region is demonstrably inconsistent with the recent high-resolution transmission data. The resonance analysis is described with the SAMMY code and the new resolved resonance parameters are discussed.
OSTI ID:
5553456
Report Number(s):
CONF-910603--
Conference Information:
Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 63
Country of Publication:
United States
Language:
English