Physical investigations of an electronuclear neutron-flux-generator target

Bol'shov, V.I.; Dubinin, A.A.; Dmitriev, V. M.; Kapchigashev, S.P.; Kon'shin, V.A.; Matusevich, E.S.; Polivanskii, V.P.; Pupko, V. Ya.; Regushevskii, V.I.; Stavisskii, Yu.Ya.; Yur'ev, Yu.S.

doi:10.1007/bf01225535

“…A reasonable estimate was made by one of the authors (SFM) using the comparative method by adopting a thermal capture cross section for 249 Bk as 746±40 b and a nuclear level density parameter a ld =29 MeV −1 for 250 Bk [2]. The result for the 2200 m/s capture cross section is 666±70 b which is consistent, within 17% uncertainty, with the JENDL-4.0 estimate but not with that of Bol'shov et al [58].…”

Section: A Neutron Thermal Cross Sectionsmentioning

confidence: 73%

“…The corresponding value in the Atlas, ∼350 b, is based on a rough estimate reported in [58]. A reasonable estimate was made by one of the authors (SFM) using the comparative method by adopting a thermal capture cross section for 249 Bk as 746±40 b and a nuclear level density parameter a ld =29 MeV −1 for 250 Bk [2].…”

Section: A Neutron Thermal Cross Sectionsmentioning

confidence: 99%

Neutron Thermal Cross Sections, Westcott Factors, Resonance Integrals, Maxwellian Averaged Cross Sections and Astrophysical Reaction Rates Calculated from the ENDF/B-VII.1, JEFF-3.1.2, JENDL-4.0, ROSFOND-2010, CENDL-3.1 and EAF-2010 Evaluated Data Libraries

Pritychenko

¹

,

Mughabghab

²

2012

Nuclear Data Sheets

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We present calculations of neutron thermal cross sections, Westcott factors, resonance integrals, Maxwellianaveraged cross sections and astrophysical reaction rates for 843 ENDF materials using data from the major evaluated nuclear libraries and European activation file. Extensive analysis of newly-evaluated neutron reaction cross sections, neutron covariances, and improvements in data processing techniques motivated us to calculate nuclear industry and neutron physics quantities, produce s-process Maxwellian-averaged cross sections and astrophysical reaction rates, systematically calculate uncertainties, and provide additional insights on currently available neutron-induced reaction data. Nuclear reaction calculations are discussed and new results are presented. Due to space limitations, the present paper contains only calculated Maxwellian-averaged cross sections and their uncertainties. The complete data sets for all results are published in the Brookhaven National Laboratory report.

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“…A reasonable estimate was made by one of the authors (SFM) using the comparative method by adopting a thermal capture cross section for 249 Bk as 746±40 b and a nuclear level density parameter a ld =29 MeV −1 for 250 Bk [2]. The result for the 2200 m/s capture cross section is 666±70 b which is consistent, within 17% uncertainty, with the JENDL-4.0 estimate but not that of Bol'shov et al [57].…”

Section: Bkmentioning

confidence: 77%

“…The ENDF/B-VII.1 file for 250 Bk is also adopted from the JENDL-4.0 evaluation, which estimated a thermal capture cross section of 780.5 b based on a computer code calculation [56]. The corresponding value in the Atlas, ∼350 b, is based on a rough estimate reported in [57]. A reasonable estimate was made by one of the authors (SFM) using the comparative method by adopting a thermal capture cross section for 249 Bk as 746±40 b and a nuclear level density parameter a ld =29 MeV −1 for 250 Bk [2].…”

Section: Bkmentioning

confidence: 99%

Neutron Thermal Cross Sections, Westcott Factors, Resonance Integrals, Maxwellian Averaged Cross Sections and Astrophysical Reaction Rates Calculated from Major Evaluated Data Libraries

Pritychenko,

Mughabghab

2012

Preprint

0

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We present calculations of neutron thermal cross sections, Westcott factors, resonance integrals, Maxwellianaveraged cross sections and astrophysical reaction rates for 843 ENDF materials using data from the major evaluated nuclear libraries and European activation file. Extensive analysis of newly-evaluated neutron reaction cross sections, neutron covariances, and improvements in data processing techniques motivated us to calculate nuclear industry and neutron physics quantities, produce s-process Maxwellian-averaged cross sections and astrophysical reaction rates, systematically calculate uncertainties, and provide additional insights on currently available neutron-induced reaction data. Nuclear reaction calculations are discussed and new results are presented. 0.4pt0.4pt 0pt0.4pt

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