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Neutron flux calculation of reactor pressure vessel for MOX fuel core

Mengqi Wang, Ding Qianxue, Qiliang Mei

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Key concepts: MOX fuel, Nuclear engineering, Reactor pressure vessel, Neutron flux, Nuclear reactor core, Core (optical fiber), Flux (metallurgy), Pressure vessel

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Neutron flux calculation of reactor pressure vessel for MOX fuel core — Research Paper | ScholarLens