Sensitivity and Uncertainty Quantification of Neutronic Integral Data Using ENDF/B-VII.1 and JENDL-4.0 Evaluations

Many integral neutronic parameters such as the effective multiplication factors (keff) are based on neutron reactions with matter through cross sections. However, these cross sections present uncertainties, of origin multiple, which reduce the safety margin of nuclear installations. In order to mini...

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Detalles Bibliográficos

Autores principales:	Makhloul, Mustapha, Boukhal, H., Bardouni, T. El, Chakir, E., Kaddour, M., Elouahdani, S.
Formato:	Capítulo de libro
Lenguaje:	inglés
Publicado:	IntechOpen 2020
Materias:	Physical Sciences, Engineering and Technology
Acceso en línea:	https://www.intechopen.com/chapters/72953
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