Beta decay properties using a statistical model

Mann, F.M.; Dunn, CD; Schenter, R.E.

doi:10.1103/physrevc.25.524

Cited by 12 publications

(12 citation statements)

References 11 publications

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“…Benchmarking of the CINDER-10 calculations contributing to ENDF/B-VI showed good agreement with measuredν d data [139]. However, application of the ENDF/B-VI temporal fits showed that the mean delayed neutron emission time following a fission event was lower by a factor of 2 to 3 than that predicted by functions fit to measurements.…”

Section: Delayed Neutronsmentioning

confidence: 65%

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ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

Chadwick

Obložinský

Herman

et al. 2006

Nuclear Data Sheets

1,962

908

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We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recommended nuclear data for advanced nuclear science and technology applications. The library, released by the U.S. Cross Section Evaluation Working Group (CSEWG) in December 2006, contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes. The new evaluations are based on both experimental data and nuclear reaction theory predictions.The principal advances over the previous ENDF/B-VI library are the following: (1) New cross sections for U, Pu, Th, Np and Am actinide isotopes, with improved performance in integral validation criticality and neutron transmission benchmark tests; (2) More precise standard cross sections for neutron reactions on H, 6 Li, 10 B, Au and for 235,238 U fission, developed by a collaboration with the IAEA and the OECD/NEA Working Party on Evaluation Cooperation (WPEC); (3) Improved thermal neutron scattering; (4) An extensive set of neutron cross sections on fission products developed through a WPEC collaboration; (5) A large suite of photonuclear reactions; (6) Extension of many neutron-and proton-induced reactions up to an energy of 150 MeV; (7) Many new light nucleus neutron and proton reactions; (8) Post-fission beta-delayed photon decay spectra; (9) New radioactive decay data; and (10) New methods developed to provide uncertainties and covariances, together with covariance evaluations for some sample cases.The paper provides an overview of this library, consisting of 14 sublibraries in the same, ENDF-6 format, as the earlier ENDF/B-VI library. We describe each of the 14 sublibraries, focusing on neutron reactions. Extensive validation, using radiation transport codes to simulate measured critical assemblies, show major improvements: (a) The long-standing underprediction of low enriched U thermal assemblies is removed; (b) The 238 U, 208 Pb, and 9 Be reflector biases in fast systems are largely removed; (c) ENDF/B-VI.8 good agreement for simulations of highly enriched uranium assemblies is preserved; (d) The underprediction of fast criticality of 233,235 U and 239 Pu assemblies is removed; and (e) The intermediate spectrum critical assemblies are predicted more accurately.We anticipate that the new library will play an important role in nuclear technology applications, including transport simulations supporting national security, nonproliferation, advanced reactor and fuel cycle concepts, criticality safety, medicine, space applications, nuclear astrophysics, and nuclear physics facility design. The ENDF/B-VII.0 library is archived at the National Nuclear Data Center,

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Section: Delayed Neutronsmentioning

confidence: 65%

“…Most precursor spectra were modeled using either the BETA code of Mann, Dunn and Schenter [139] or an evaporation spectrum. Detailed fine-binned spectra were accumulated for the six temporal groups by assigning contributions of each precursor to neighboring temporal groups while enforcing maximum likelihood to total spectra.…”

Section: Delayed Neutronsmentioning

confidence: 99%

ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

Chadwick

Obložinský

Herman

et al. 2006

Nuclear Data Sheets

1,962

908

View full text Add to dashboard Cite

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“…The statistical theory has been applied to calculate the decay probabilities of the excited states in the past [4][5][6][7][8]. However, due to the lack of detailed nuclear-structure calculations and approximations made for the neutron and γ -ray penetration probabilities, these studies only reproduce the general trend of the experimental data.…”

Section: B Neutron Emission From Excited Statesmentioning

confidence: 99%

“…(2). The ENDF/B-VI evaluation for 80 Ga is based on experimental data [26][27][28] in the energy range 100 keV-1.05 MeV, and the BETA code [8] was employed to extrapolate the spectrum outside the range [3]. Because our calculations consider all the possible transitions between the excited states in the daughter and granddaughter nuclei, the details of the complicated structure in the experimental spectra, which cannot be reproduced by an evaporation or Maxwellian spectrum [29], are present in our results.…”

Section: A Structure In Neutron Spectramentioning

confidence: 99%

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Calculation of delayed-neutron energy spectra in a quasiparticle random-phase approximation–Hauser-Feshbach model

2008

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Theoretical β-delayed-neutron spectra are calculated based on the Quasiparticle Random-Phase Approximation (QRPA) and the Hauser-Feshbach statistical model. Neutron emissions from an excited daughter nucleus after β decay to the granddaughter residual are more accurately calculated than in previous evaluations, including all the microscopic nuclear structure information, such as a Gamow-Teller strength distribution and discrete states in the granddaughter. The calculated delayed-neutron spectra agree reasonably well with those evaluations in the ENDF decay library, which are based on experimental data. The model was adopted to generate the delayed-neutron spectra for all 271 precursors.

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High resolution measurements of time-dependent integral delayed neutron spectra from thermal neutron induced fission of 235 U

Piksaikin

Egorov

Goverdovski

et al. 2017

Annals of Nuclear Energy

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Beta decay properties using a statistical model

Cited by 12 publications

References 11 publications

ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

Calculation of delayed-neutron energy spectra in a quasiparticle random-phase approximation–Hauser-Feshbach model

High resolution measurements of time-dependent integral delayed neutron spectra from thermal neutron induced fission of 235 U

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