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Cited article:

Assessment of neutron kerma coefficients and its calculation methodologies using recent basic ENDF-6 libraries

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Nuclear Engineering and Design 360 110519 (2020)
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TENDL: Complete Nuclear Data Library for Innovative Nuclear Science and Technology

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Nuclear Data Sheets 155 1 (2019)
https://doi.org/10.1016/j.nds.2019.01.002

Impact of Nuclear Data Uncertainty in the Modeling of Neutron-Induced Recoil Atom Energy Distributions in Silicon

Patrick J. Griffin, Arjan J. Koning and Dimitri Rochman
IEEE Transactions on Nuclear Science 66 (7) 1719 (2019)
https://doi.org/10.1109/TNS.2019.2894730

An estimation of neutron-induced production of gases with propagation of uncertainties in nuclear data for structural materials of fission and fusion reactors

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Journal of Nuclear Materials 519 88 (2019)
https://doi.org/10.1016/j.jnucmat.2019.03.040

Neutron-induced damage simulations: Beyond defect production cross-section, displacement per atom and iron-based metrics

J. -Ch. Sublet, I. P. Bondarenko, G. Bonny, et al.
The European Physical Journal Plus 134 (7) (2019)
https://doi.org/10.1140/epjp/i2019-12758-y

Propagation of uncertainties in basic nuclear reaction data to uncertainties in the parameters of primary radiation damage by neutrons

Uttiyoarnab Saha, K. Devan and S. Ganesan
Journal of Nuclear Materials 510 43 (2018)
https://doi.org/10.1016/j.jnucmat.2018.07.045