Neutron Cross Section Covariances for Structural Materials and Fission Products

Hoblit, S.; Cho, Y.-S.; Herman, M.; Mattoon, Caleb; Mughabghab, S.F.; Obložinský, P.; Pigni, Marco T.; Sonzogni, A. A.

doi:10.1016/j.nds.2011.11.006

Cited by 6 publications

(2 citation statements)

References 22 publications

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“…This analysis includes over 843 isotopic and elemental neutron evaluations of importance to the wide range of applications. The present paper uses ENDF/B-VII.1 [1,[12][13][14][15] and Low-Fidelity neutron cross section covariance data [17,18], to provide uncertainty estimates. An extensive discussion on neutron parameter calculations, potential implications and further recommendations are presented.…”

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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

Mughabghab

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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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

Mughabghab

2012

Nuclear Data Sheets

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“…The covariance files are essential in uncertainty quantification processes driven by nuclear model and experimental user needs. An extensive CSEWG covariance development effort [23,24] furnished multiple results.…”

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confidence: 99%

The use of the ENDF library for nucleosynthesis studies

Pritychenko

2020

EPJ Web Conf.

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Stellar nucleosynthesis modeling studies would significantly benefit from the use of fully traceable, documented and unbiased nuclear data. The nuclear industry standard Evaluated Nuclear Data File (ENDF) libraries contain extensive collections of reaction data sets relevant to astrophysics. For the first time rapid-and slow-neutron capture, r- and s-process, respectively, abundances were computed from ENDF/B-VIII.0 and TENDL-2015 libraries and compared with available data. The current results highlight mutually beneficial relations between nuclear industry and nuclear astrophysics data developments.

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Optimization of the radiation shielding capabilities of bismuth-borate glasses using the genetic algorithm

Wilson

2019

Materials Chemistry and Physics

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Neutron Cross Section Covariances for Structural Materials and Fission Products

Cited by 6 publications

References 22 publications

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

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

The use of the ENDF library for nucleosynthesis studies

Optimization of the radiation shielding capabilities of bismuth-borate glasses using the genetic algorithm

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