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

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DC Field	Value	Language
dc.contributor.author	SHAFII, Mohammad Ali	-
dc.contributor.author	ZAKIYA, Imra	-
dc.contributor.author	FITRIYANI, Dian	-
dc.contributor.author	ARKUNDATO, Artoto	-
dc.contributor.author	ABDULLAH, Ade Gafar	-
dc.date.accessioned	2023-05-10T03:36:48Z	-
dc.date.available	2023-05-10T03:36:48Z	-
dc.date.issued	2022-09-20	-
dc.identifier.uri	https://repository.unej.ac.id/xmlui/handle/123456789/116018	-
dc.description.abstract	neutron flux distribution is an essential parameter inthe neutronic analysis of the neutron transport in the nuclear reactor	en_US
dc.language.iso	en	en_US
dc.publisher	AIP Conference Proceedings	en_US
dc.subject	neutron flux distribution of slab reactor core	en_US
dc.title	Neutron FLux Distribution of Slab Reactor Core using One-Dimensional Multi-Group Diffusion Multi-Group Diffusion Equation inthe Thermal Energy Region	en_US
dc.type	Article	en_US
Appears in Collections:	LSP-Conference Proceeding

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