Open AccessNeutron Mean Free Path in the Slab Reactor Core using One-Dimensional Multi-group Diffusion Equation
Author(s) -
Putri Nabila,
Mohammad Ali Shafii,
Seni H. J. Tongkukut
Publication year - 2022
Publication title -
computational and experimental research in materials and renewable energy
Language(s) - English
Resource type - Journals
ISSN - 2747-173X
DOI - 10.19184/cerimre.v5i1.31566
Subject(s) - neutron flux , mean free path , neutron temperature , neutron , neutron transport , nuclear reactor core , neutron cross section , nuclear physics , physics , slab , diffusion , thermodynamics , geophysics , electron