Neutron Mean Free Path in the Slab Reactor Core using One-Dimensional Multi-group Diffusion Equation

Neutron Mean Free Path in the Slab Reactor Core using One-Dimensional Multi-group Diffusion Equation

Analysis of the neutron mean free path in the slab reactor core has been carried out using one-dimensional multi-group diffusion equation. This study aims to determine the neutron mean free path in the slab reactor core with the neutron diffusion coefficient calculation using macroscopic cross-secti...

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Bibliographic Details
Main Authors: Putri Nabila, Mohammad Ali Shafii, Seni Herlina J. Tongkukut
Format: Article
Language:English
Published: Physics Department, Faculty of Mathematics and Natural Sciences University of Jember 2022-05-01
Series:Computational and Experimental Research in Materials and Renewable Energy
Online Access:https://jurnal.unej.ac.id/index.php/CERiMRE/article/view/31566

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