Measurement of Highly Active Isotope Fission Cross Sections with Nuclear Explosion Neutrons

Fomushkin, E.F.; Novoselov, G. F.; Gavrilov, V. V.; Vinogradov, Ju. I.

doi:10.1007/978-3-642-58113-7_123

Cited by 4 publications

(4 citation statements)

References 3 publications

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“…18 Top: total, elastic, inelastic, fission and capture cross sections for 244 Cm compared to the Gianotti model calculations [106] and the measurements [107][108][109][110][111][112]. Bottom: fission and capture cross sections for 244 Cm compared to the JENDL-4.0 and ENDF/B-VII.1 evaluations, the Gianotti model calculations [106] and the measurements [107][108][109][110][111][112] used. Fission cross sections were derived in the WKB approximation supposing a double-humped fission barrier with free parameters that were adjusted to experimental cross section data [99].…”

Section: Curiummentioning

confidence: 99%

“…[107][108][109][110][111][112]. The correlation of total and fission cross sections for 244 Cm and the uncertainties compared to the measurements [106][107][108][109][110][111][112][113][114][115][116][117][118][119] Covariance data were generated by the Kalman code implemented in the EMPIRE system supposing a 10% uncertainty on the model parameters. These uncertainties were complemented in a Bayesian updating procedure with the experimental fission cross section data listed in Table 11.…”

Section: Curiummentioning

confidence: 99%

“…An ENDF-6 compatible evaluation for neutron induced reactions in the resonance region has been completed for 106,108,110,111,112,113,114,116 Cd. The resonance parameters were derived from an analysis of experimental data available in the literature together with a parameter adjustment to transmission and capture data obtained at the time-of-flight facility GELINA.…”

Section: Cadmiummentioning

confidence: 99%

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The joint evaluated fission and fusion nuclear data library, JEFF-3.3

et al. 2020

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The joint evaluated fission and fusion nuclear data library 3.3 is described. New evaluations for neutroninduced interactions with the major actinides 235 U, 238 U and 239 Pu, on 241 Am and 23 Na, 59 Ni, Cr, Cu, Zr, Cd, Hf, W, Au, Pb and Bi are presented. It includes new fission yields, prompt fission neutron spectra and average number of neutrons per fission. In addition, new data for radioactive decay, thermal neutron scattering, gamma-ray emission, neutron activation, delayed neutrons and displacement damage are presented. JEFF-3.3 was complemented by files from the TENDL project. The libraries for photon, proton, deuteron, triton, helion and alpha-particle induced reactions are from TENDL-2017. The demands for uncertainty quantification in modeling led to many new covariance data for the evaluations. A comparison between results from model calculations using the JEFF-3.3 library and those from benchmark experiments for criticality, delayed neutron yields, shielding and decay heat, reveals that JEFF-3.3 performes very well for a wide range of nuclear technology applications, in particular nuclear energy.

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Section: Curiummentioning

confidence: 99%

Section: Curiummentioning

confidence: 99%

Section: Cadmiummentioning

confidence: 99%

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The joint evaluated fission and fusion nuclear data library, JEFF-3.3

et al. 2020

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“…Concerning 244 Cm, we took account of the measured fission cross sections 11,12,21,[28][29][30] given in Table 3 for the GMA analysis above 1 keV. The data reported before 1970 were ignored in the present work.…”

Section: )mentioning

confidence: 99%