1977
DOI: 10.1103/physrevc.15.2083
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Intermediate structure studies ofU234cross sections

Abstract: Neutron induced fission and total cross sections of "-"U have been measured over the neutron energy range from a few eV to 8.9 MeV. Neutron and fission widths for 118 cross section resonances below 1500 eV have been determined and give a class I level spacing of ]0.6+0.5 eV and an s-wave strength function of (0.86+ 0.11) g 10 '. These fine structure resonances form two narrow intermediate structure resonances in the subthreshold fission cross section of '"U. Parameters for the Lorentzian energy dependence of t… Show more

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Cited by 41 publications
(19 citation statements)
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“…5 by comparison with the data of Refs. [39,40] and with evaluated data [35][36][37]. In general, there is fair agreement with the ENDF/B-VII evaluation except that resonance multiplets could now be resolved by the present data and a slight displacement of the resonance position is observed with respect to evaluated resonances.…”
Section: A Resonance Regionsupporting
confidence: 86%
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“…5 by comparison with the data of Refs. [39,40] and with evaluated data [35][36][37]. In general, there is fair agreement with the ENDF/B-VII evaluation except that resonance multiplets could now be resolved by the present data and a slight displacement of the resonance position is observed with respect to evaluated resonances.…”
Section: A Resonance Regionsupporting
confidence: 86%
“…[42] 034601-6 In Tables IV and V the averaged cross section in wider energy intervals is compared with the evaluations and the previous data. In the resolved resonance region, our values for 234 U are about 27% above the results obtained by James et al [39]. Beyond 1.5 keV, the differences are greater up to [42], and Plattard [43].…”
Section: A Resonance Regionsupporting
confidence: 42%
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“…The ENDF/B-VII.1 and JENDL-4.0 evaluations are shifted in energy and some resonances are missing in one of the two databases. In the Resolved Resonance Region (RRR), both evaluations are based on the experimental data of James et al [3], but JENDL-4.0 includes also the resonance parameters provided by Dridi et al [4] for the capture reaction and the fission cross section of Heyse et al [5] for the 5.17 eV resonance. Above 1.5 keV, in the Unresolved Resonance Region (URR), the fission data of James et al and the capture data of Pennington were used in ENDF/B-VII.1 whereas JENDL-4.0 used the experimental data sets mentioned in Ref.…”
Section: Introductionmentioning
confidence: 99%
“…Ever increasing computing capabilities have made possible more exact calculations of the average fission cross section, using a Monte Carlo sampling of energies, fission and coupling widths of the class-II states as well as the characteristics of the class-I states from the statistical distribution of levels and partial widths. A few attempts were made in the past [4,5], but the most significant application of this method was performed in 2002 by Lynn and Hayes [6] over a wide range of actinide fission cross sections. In addition to better predict the magnitude of the cross section, this Monte Carlo approach paves the way for modeling genuine fluctuations in the Unresolved Resonance energy Range (at the right energies and with correct fluctuation envelopes) and provides a more a e-mail:…”
Section: Introductionmentioning
confidence: 99%