Neutron FLux Distribution of Slab Reactor Core using One-Dimensional Multi-Group Diffusion Multi-Group Diffusion Equation inthe Thermal Energy Region

Please use this identifier to cite or link to this item: https://repository.unej.ac.id/xmlui/handle/123456789/116018

Title:	Neutron FLux Distribution of Slab Reactor Core using One-Dimensional Multi-Group Diffusion Multi-Group Diffusion Equation inthe Thermal Energy Region
Authors:	SHAFII, Mohammad Ali ZAKIYA, Imra FITRIYANI, Dian ARKUNDATO, Artoto ABDULLAH, Ade Gafar
Keywords:	neutron flux distribution of slab reactor core
Issue Date:	20-Sep-2022
Publisher:	AIP Conference Proceedings
Abstract:	neutron flux distribution is an essential parameter inthe neutronic analysis of the neutron transport in the nuclear reactor
URI:	https://repository.unej.ac.id/xmlui/handle/123456789/116018
Appears in Collections:	LSP-Conference Proceeding

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