Summary of the Workshop on Neutron Cross Section Covariances
References (9)
- et al.
ENDF/B-VII. 0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology
Nuclear Data Sheets
(2006) - R.W. Peelle, Report ANL-76-90, Argonne National Laboratory,...
- Evaluated Nuclear Data Library, ENDF/B-VI (1990), National Nuclear Data Center,...
International Conference on Nuclear Data for Science and Technology
There are more references available in the full text version of this article.
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Calculations of Maxwellian-averaged cross sections and astrophysical reaction rates using the ENDF/B-VII.0, JEFF-3.1, JENDL-3.3, and ENDF/B-VI.8 evaluated nuclear reaction data libraries
2010, Atomic Data and Nuclear Data TablesCitation Excerpt :This represents a significant drawback for the current approach. The lack of neutron cross section covariance data is well recognized by the ENDF community [43] and extensive work is underway worldwide [44–48] to remedy this situation. The ENDF/B-VII neutron cross section covariances are scheduled for release with the ENDF/B-VII.1 library in December 2011.
Neutron activation cross sections for zirconium isotopes
2010, Nuclear Physics AUncertainty quantification in the Nuclear Data Program
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2009, Nuclear Engineering and Technology
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