Abstract
.Cross sections for neutron interactions with 238U in the energy region from 5keV to 150keV have been evaluated. Average total and capture cross sections have been derived from a least squares analysis using experimental data reported in the literature. The resulting cross sections have been parameterised in terms of average resonance parameters maintaining full consistency with results of optical model calculations by using a dispersive coupled channel optical model potential. The average compound partial cross sections have been expressed in terms of transmission coefficients by applying the Hauser-Feshbach statistical reaction theory including width-fluctuations. A generalized single-level representation compatible with the energy-dependent options of the ENDF-6 format has been applied using standard boundary conditions. The results have been transferred into a full ENDF-6 compatible data file.
Highlights
Cross sections for neutron interactions with 238U in the energy region from 5 keV to 150 keV have been evaluated
In the energy region below 150 keV differences of more than 5% are observed [1] between the average capture cross sections in the main data libraries, i.e. ENDF/B-VII.1, JEFF-3.2 and JENDL4, and the one recommended by Carlson et al [4]
Results of high resolution time-of-flight (TOF) total cross section a e-mail: peter.schillebeeckx@ec.europa.eu measurements carried out by Harvey et al [5] have not been included in previous evaluations for the unresolved resonance region (URR), e.g. in the evaluation performed by Frohner [2,3], Maslov et al [6] and Courcelle et al [7]
Summary
The results of the present work have been included in the evaluated data file for neutron induced reactions on 238U reported by Capote et al [13].
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