Neutronic analysis for core conversion (HEU–LEU) of the low power research reactor using the MCNP4C code

Neutronic analysis for core conversion (HEU–LEU) of the low power research reactor using the MCNP4C code

Comparative studies for conversion of the fuel from HEU to LEU in the miniature neutron source reactor (MNSR) have been performed using the MCNP4C code. The HEU fuel (UAl4-Al, 90% enriched with Al clad) and LEU (UO2 12.6% enriched with zircaloy-4 alloy clad) cores have been analyzed in this study. T...

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Bibliographic Details
Main Authors: Aldawahra Saadou, Khattab Kassem, Saba Gorge
Format: Article
Language:English
Published: Sciendo 2015-06-01
Series:Nukleonika
Subjects:
mnsr reactor
heu fuel
leu fuel
mcnp4c code
safety parameters
Online Access:https://doi.org/10.1515/nuka-2015-0037

Internet

https://doi.org/10.1515/nuka-2015-0037

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