Neutron flux distribution of slab reactor core using one-dimensional multi-group diffusion equation in the thermal energy region

Shafii, Mohammad Ali; Zakiya, Imra; Fitriyani, Dian; Arkundato, Artoto; Abdullah, Ade Gafar

doi:10.1063/5.0108170

The 3rd International Conference on Physical Instrumentation and Advanced Materials (Icpiam) 2021

2022

DOI: 10.1063/5.0108170

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Neutron flux distribution of slab reactor core using one-dimensional multi-group diffusion equation in the thermal energy region

Mohammad Ali Shafii

Imra Zakiya

Dian Fitriyani

et al.

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Calculation of neutron flux distribution and diffusion coefficient in the slab reactor core using multi-group diffusion equation with Jacobi method

Shafii,

Muldarisnur,

Tongkukut

et al. 2024

The 7TH INTERNATIONAL CONFERENCE ON SCIENCE AND TECHNOLOGY (ICST22): Smart Innovation Research on Science and Technology for a

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Calculation of neutron flux distribution and diffusion coefficient in the slab reactor core using multi-group diffusion equation with Jacobi method

Shafii,

Muldarisnur,

Tongkukut

et al. 2024

The 7TH INTERNATIONAL CONFERENCE ON SCIENCE AND TECHNOLOGY (ICST22): Smart Innovation Research on Science and Technology for a

View full text Add to dashboard Cite

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Neutron flux distribution of slab reactor core using one-dimensional multi-group diffusion equation in the thermal energy region

Cited by 1 publication

References 10 publications

Calculation of neutron flux distribution and diffusion coefficient in the slab reactor core using multi-group diffusion equation with Jacobi method

Calculation of neutron flux distribution and diffusion coefficient in the slab reactor core using multi-group diffusion equation with Jacobi method

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