A simultaneous evaluation of the fission cross-sections of U-235, Pu-239 and U-238 and the capture cross-section of U-238 in the energy range 100 eV to 20 MeV

Neutron Resonance Parameters of 238U and the Calculated Cross Sections from the Reich-Moore Analysis of Experimental Data in the Neutron Energy Range from 0 keV to 20 keV

“…The average capture cross sections inferred by 238 de Saussure et al from their experimental data were much larger than the results of the evaluation performed at the same time (ENDF/B-III or Sowerby evaluation ). The average values published 23 by Macklin et al were not corrected for self-shielding and multiple-scattering effects, and could 4 not be compared to any other results. The large background and normalization corrections found by Sowerby and Moxon for the de Saussure data and the Macklin data were confirmed by the 1 present work.…”

Updating the 238U(n,2n), 238U(n,3n), 238U(n,4n) and 238U(n,elastic) ENDL Cross Sections

“…12459004 [12] Discarded, don't understand point even after applying correction for bad monitor. 20416021 [13] Replaced [8] 238 U(n, f ) evaluation with that in [7] in rescaling. 20499002 [14] OK 20794013 [15] OK 20795012 [16] Replaced bad monitor with 238 U(n, f ) evaluation in [7], dropped last point.…”

“…20499002 [14] OK 20794013 [15] OK 20795012 [16] Replaced bad monitor with 238 U(n, f ) evaluation in [7], dropped last point. 21019025 [17] OK 21208003 [18] OK 21521003 [19] OK 21568003 [20] Replaced [8] 238 U(n, f ) evaluation with that in [7] [28] Discarded, it is fission spectrum averaged with unknown spectrum. 41147007 [29] Discarded, it is spectrum averaged with unknown spectrum.…”

EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5

“…But a more sophisticated way is to treat absolute cross sections (e.g., 239 Pu and 235 U fission cross sections) and their ratio (e.g., 239 Pu/ 235 U fission cross section ratio) in an equivalent manner without converting one to the other. Sowerby et al [10,11] and Poenitz [12] are known as pioneers in this approach, and the JENDL project also has adopted this technique since its early versions. In its first attempt for the JENDL-2 library, evaluation of the 235,238 U and 239,240,241 Pu(n,f) cross sections from 100 eV to 20 MeV was divided into three steps -(1) preliminary evaluation for 235 U, (2) normalization and evaluation for other target nuclides by using the preliminary 235 U evaluation result, and (3) reevaluation for 235 U to meet the requirements from the second step -to maintain consistency between the cross sections of all nuclides [13,14].…”