Cross section for the reaction 238U(n, γ)239U in the energy range 0·12–7·6 MeV

Cross-sections of the 238U (n, γ) 239U reaction in the 3.0–7.0 MeV energy region measured by relative activation method*

“…It can be clearly demonstrated that there are significant differences between the evaluation databases for the neutron energies in the range of 3.0-7.0 MeV. Within this energy region, the experimental values of Panitkin et al [24] are more compatible with the cross-sectional values of the database CENDL-3.2 and superior to those of ROSFOND-2010 and ENDF/B-VIII.0. In addition, the results of this experiment at neutron energies of 3.622 ± 0.348 MeV, 4.626 ± 0.086 MeV, and 6.117 ± 0.119 MeV are in accordance with the evaluation data of ENDF/B-VIII.0 but marginally higher and in general agreement with the theoretical calculation results of TALYS-1.9.…”

“…Moreover, it is apparent that there are substantial variations among the evaluation databases for this energy region with three distinct tendencies; in particular, the ENDF/B-VIII.0 [26] and CENDL-3.2 [27] databases reach a maximum difference of 81.2% at a neutron energy of 7 MeV. The experimental values obtained by Panitkin et al [24] are compatible with the evaluation database CENDL-3.2 but are superior to the ENDF/B-VIII.0 and ROSFOND-2010 [28] databases in the 3.0-7.0 MeV energy region. In contrast, the experimental measurements of Mulik et al [4] at 5.9 ± 0.5 MeV neutron energy and the data of S.Mukherjee et al [7] at 5.1 ± 0.2 MeV are in general accordance with the evaluation databases ENDF/B-VIII.0 and ROSFOND-2010, respectively, yet far inferior to the evaluation data of CENDL-3.2.…”

EVALUATION OF $sup 238$U NEUTRON CROSS SECTIONS FOR THE ENDF/B VERSION II FILE.

“…Above 100 keV, the majority of accurate capture measurements are relative to 235u fission, such as Barry [21] and Poenitz [22,23], while the Menlove and Poenitz [24] data can be placed relative to ^^^U fission by use of the fission cross section of Poenitz [25] obtained by the same experimental techniques. These four sets of data were normalized to the ENDF/B [18,26] ^^^U fission cross section and are shown in Figure 1.…”