Statistical analysis of experimental data on the cross sections of233,235,238U,237Np,239,242Pu fission by neutrons of energy 2.6, 8.5, and 14.5 MeV

Dushin, V. N.; Фомичев, А. В.; Kovalenko, S. S.; Petrzhak, K.A.; Shpakov, V.I.; Arlt, R.; Iosh, M.; Muzioł, G.; Ortlepp, Kh.-G.; Vagner, V.

doi:10.1007/bf01124127

Cited by 8 publications

(5 citation statements)

References 4 publications

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“…6. 235 U fission prior and posterior cross sections with the experimental cross sections used for evaluation [52][53][54][70][71][72][73][74][75][76][77][78][79][80][81][82][83][84][85][86]. The prior cross section is taken from JENDL-4.0 (below 20 MeV) and JENDL-4.0/HE (above 20 MeV).…”

Section: Resultsmentioning

confidence: 99%

“…The tables of Ref. [52] show there are several measurements for the same target nuclide and incident energy in some cases, and this makes selection of the data points without double counting very difficult. We traced the history of the measurements at TUD, KRI and ZFK (Zentralinstitut für Kernforschung, Rossendorf) by reviewing all journal articles and reports compiled in CINDA (Comprehensive Index of Nuclear Reaction Data) [159], and selected the data points listed in Table III as inputs to our analysis.…”

Section: Exclusion Of Duplicated Data Points From Tud-kri Collaborationmentioning

confidence: 99%

Section: Modification To Exfor Entriesmentioning

confidence: 99%

“…• 233,235,238 U and 239 Pu by Dushin et al [52] (EXFOR 51001 3 ) Prepared to collect the absolute fission cross sections measured by the associated particle method at KRI assuming that the KRI data points tabulated in Ref. [52] are the final ones (See also Table III). The covariance matrices published in this reference were converted to the correlation coefficients, and used as inputs to our evaluation.…”

Section: Modification To Exfor Entriesmentioning

confidence: 99%

“…Correlation coefficients are explicitly given under the keyword covariance in the EXFOR entry for a few cases (EXFOR 13169.002 [91], 14498.002 [99], 22211.002 [142], 22282.003.1 and 006.1 [64], 41112.002 [75], 51001.002-005 [52], 51006.002 [70] ) and they were directly taken as inputs to our fitting.…”

Section: • Correlation Coefficients In Exformentioning

confidence: 99%

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

Otuka,

Iwamoto

2022

Preprint

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The neutron-induced fission cross sections were simultaneously evaluated for the JENDL-5 library for 233,235 U and 239,241 Pu from 10 keV to 200 MeV and for 238 U and 240 Pu from 100 keV to 200 MeV. Evaluation was performed by least-squares fitting of Schmittroth's roof function to the logarithms of the experimental cross sections and cross section ratios in the EXFOR library. A simultaneous evaluation code SOK was used with its extension to data in arbitrary unit. The outputs of the code were adopted as the evaluated cross sections without any further corrections. The newly obtained evaluated cross sections were compared with the evaluated cross sections in the JENDL-4.0 library and the IAEA Neutron Data Standards 2017. The evaluated cross sections were also validated against the californium-252 spontaneous fission neutron spectrum averaged cross sections, ΣΣ (coupled thermal/fast uranium and boron carbide spherical assembly) neutron spectrum averaged cross sections, and small-sized LANL fast system criticalities. The changes in the obtained evaluated cross sections from those in the JENDL-4.0 library are within 4% ( 241 Pu), 3% ( 233 U, 240 Pu), or 2% ( 235 U, 239 Pu). The newly evaluated 235 U, 238 U and 239 Pu cross sections agree with the IAEA Neutron Data Standards 2017 within 2% with some exceptions.(This is a preprint of N. Otuka and O. Iwamoto, J. Nucl. Sci. Technol., to be published online as an open access article.)

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