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Evaluated Nuclear Data

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Handbook of Nuclear Engineering

Abstract

This chapter describes the current status of evaluated nuclear data for nuclear technology applications. We start with evaluation procedures for neutron-induced reactions focusing on incident energies from the thermal energy up to 20 MeV, though higher energies are also mentioned. This is followed by examining the status of evaluated neutron data for actinides that play a dominant role in most of the applications, followed by coolants/moderators, structural materials, and fission products. We then discuss neutron covariance data that characterize uncertainties and correlations. We explain how modern nuclear evaluated data libraries are validated against an extensive set of integral benchmark experiments. Afterward, we briefly examine other data of importance for nuclear technology, including fission yields, thermal neutron scattering, and decay data. A description of three major evaluated nuclear data libraries is provided, including the latest version of the US library ENDF/B-VII.0, European JEFF-3.1, and Japanese JENDL-3.3. A brief introduction is made to current web retrieval systems that allow easy access to a vast amount of up-to-date evaluated nuclear data for nuclear technology applications.

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Acknowledgements

It would not have been possible to write this chapter without results produced by the dedicated work of numerous scientists and colleagues over years, both in the USA and abroad. We are particularly grateful to members of CSEWG and many other colleagues who contributed to ENDF/B-VII.0 and other nuclear data libraries. We owe special thanks to the authors of the “Big Paper” on ENDF/B-VII.0 (Chadwick et al., 2006), which supplied most of the figures and served as the basis for preparing this chapter.

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  1. National Nuclear Data Center, Brookhaven National Laboratory, Upton, NY, USA

    Pavel Obložinský, Michal Herman & Said F. Mughabghab

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  1. Pavel Obložinský
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  2. Michal Herman
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  1. Institute for Nuclear Technology and Reactor Safety, Karlsruher Institut fur Technologie (KIT), Gotthard-Franz-Str. 9, 76131, Karlsruhe, Germany

    Dan Gabriel Cacuci

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Obložinský, P., Herman, M., Mughabghab, S.F. (2010). Evaluated Nuclear Data. In: Cacuci, D.G. (eds) Handbook of Nuclear Engineering. Springer, Boston, MA. https://doi.org/10.1007/978-0-387-98149-9_2

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