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pro vyhledávání: '"I Ibrahim Bashter"'
Publikováno v:
Nuclear Technology and Radiation Protection, Vol 34, Iss 4, Pp 325-335 (2019)
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 AP100