Effect of MOX fuel and the ENDF/B-VIII on the AP1000 neutronic parameters calculations by using MCNP6

Effect of MOX fuel and the ENDF/B-VIII on the AP1000 neutronic parameters calculations by using MCNP6

The present work studies the effect of introducing MOX fuel on Westinghouse AP1000 neutronic parameters. The neutronic calculations were performed by using the MCNP6 code with the ENDF/B-VII.1 library and the new release of the ENDF/B-VIII, the AP1000 core with three 235U enrichment zon...

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Bibliographic Details
Main Authors: Reda Sonia M., Gomaa Ibrahim M., Bashter Ibrahim I., Amin Esmat A.
Format: Article
Language:English
Published: VINCA Institute of Nuclear Sciences 2019-01-01
Series:Nuclear Technology and Radiation Protection
Subjects:
ap1000 reactor
mox fuel
neutronic parameters
mcnp6
endf/b-viii
Online Access:http://www.doiserbia.nb.rs/img/doi/1451-3994/2019/1451-39942000002R.pdf

Internet

http://www.doiserbia.nb.rs/img/doi/1451-3994/2019/1451-39942000002R.pdf

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