Analysis of the Fission and Capture Cross Sections of the Curium Isotopes

Moore, M. S.; Keyworth, G.A.

doi:10.1103/physrevc.3.1656

Cited by 64 publications

(61 citation statements)

References 18 publications

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“…The fission widths are subsequently derived on the basis of an assumed average capture width, as, for example, in the case of the isotopic curium measurements of [8]. In this case ρ(Γ f , Γ γ ) is positive.…”

Section: Some Sources Of Correlationsmentioning

confidence: 99%

Neutron Cross Section Uncertainties in the Thermal and Resonance Regions

Mughabghab

Obložinský

2008

Nuclear Data Sheets

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In the Atlas of Neutron Resonances, special care was expended to ensure that the resonance parameter information reproduces the various measured thermal cross sections, as well as the infinite dilute resonance integrals for Z = 1-100. In contrast, the uncertainties of the recommended quantities do not match those generated from the uncertainties of the resonance parameters. To address this problem, the present study was initiated to achieve consistency for 15 actinides and 21 structural and coolant moderator materials. This is realized by assigning uncertainties to the parameters of the negative-energy resonances and changing, if necessary, significantly the uncertainties of the low-lying positive-energy resonances. The influence of correlations between parameters on the derived uncertainties is examined and discussed.

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Section: Some Sources Of Correlationsmentioning

confidence: 99%

Neutron Cross Section Uncertainties in the Thermal and Resonance Regions

Mughabghab

Obložinský

2008

Nuclear Data Sheets

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“…The agreement with the data of White et al [7] is also reasonable. In this energy range the evaluated cross sections are essentially based on the results of Moore and Keyworth [5]. Consequently, they generally adequately reproduce the cross section measured at n TOF as well.…”

Section: Normalization and Resultsmentioning

confidence: 90%

“…For neutron energies above 20 eV, data from Moore and Keyworth [5] are also available. In general, the n TOF results are in very good agreement with this last data set, which was obtained with a collimated neutron beam from a nuclear explosion (Fig.…”

Section: Normalization and Resultsmentioning

confidence: 99%

“…In 1969 Moore and Keyworth [5] reported data from 20 eV to 3 MeV by using a nuclear explosion as the neutron source. The measurement of Browne et al [6] in 1978 at the 100 MeV electron linear accelerator at Lawrence Livermore National Laboratory covered the neutron energy range between 0.01 and 35 eV.…”

Section: Introductionmentioning

confidence: 99%

“…The cross sections in these libraries are all essentially based on the same evaluation [13], which relied on the data of Browne et al [6] up to 20 eV and on the data 034616-2 of Moore and Keyworth [5] at higher energy. A different approach was used in JENDL-4 [14], as well as in the special purpose file JENDL/AC-2008 [15], a specialized version of JENDL containing only data on actinides needed for advanced reactor technology (since the two files are equivalent for actinides, in the following we will only refer to the latter).…”

Section: Introductionmentioning

confidence: 99%

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Neutron-induced fission cross section of245Cm: New results from data taken at the time-of-flight facility n_TOF

Calviani¹,

Meaze²,

Colonna³

et al. 2012

Phys. Rev. C

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The neutron-induced fission cross section of 245 Cm was measured at n TOF in a wide energy range and with high resolution. The energy dependence, measured in a single measurement from 30 meV to 1 MeV neutron energy, has been determined with 5% accuracy relative to the 235 U(n,f) cross section. In order to reduce the uncertainty on the absolute value, the data have been normalized at thermal energy to recent measurements performed at ILL and BR1. In the energy range of overlap, the results are in fair agreement with some previous measurements and confirm, on average, the evaluated cross section in the ENDF/B-VII.0 database, although sizable differences are observed for some important resonances below 20 eV. A similar behavior is observed relative to JENDL/AC-2008, a reactor-oriented database for actinides. The new results contribute to the overall improvement of the databases needed for the design of advanced reactor systems and may lead to refinements of fission models for the actinides.

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Table of Values

Hirano¹

2017

Friction at the Atomic Level

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Analysis of the Fission and Capture Cross Sections of the Curium Isotopes

Cited by 64 publications

References 18 publications

Neutron Cross Section Uncertainties in the Thermal and Resonance Regions

Neutron Cross Section Uncertainties in the Thermal and Resonance Regions

Neutron-induced fission cross section of245Cm: New results from data taken at the time-of-flight facility n_TOF

Table of Values

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