Calculation of neutron flux and neutron visualization in a spherical reactor core applying a conceptual approach and drawing a comparison with the results obtained by the CITATION code

Shirazi, Seyed Alireza Mousavi

doi:10.1016/j.jandt.2021.09.006

International Journal of Advanced Nuclear Reactor Design and Te

2021

DOI: 10.1016/j.jandt.2021.09.006

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Calculation of neutron flux and neutron visualization in a spherical reactor core applying a conceptual approach and drawing a comparison with the results obtained by the CITATION code

Seyed Alireza Mousavi Shirazi¹

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Assessment of the IEA-R1 nuclear reactor using a nonstandard fuel assembly with six fuel plates of the Brazilian Multipurpose Reactor

Soares,

Torres,

Umbehaun

et al. 2024

Nuclear Engineering and Design

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Assessment of the IEA-R1 nuclear reactor using a nonstandard fuel assembly with six fuel plates of the Brazilian Multipurpose Reactor

Soares,

Torres,

Umbehaun

et al. 2024

Nuclear Engineering and Design

View full text Add to dashboard Cite

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Calculation of neutron flux and neutron visualization in a spherical reactor core applying a conceptual approach and drawing a comparison with the results obtained by the CITATION code

Cited by 1 publication

References 10 publications

Assessment of the IEA-R1 nuclear reactor using a nonstandard fuel assembly with six fuel plates of the Brazilian Multipurpose Reactor

Assessment of the IEA-R1 nuclear reactor using a nonstandard fuel assembly with six fuel plates of the Brazilian Multipurpose Reactor

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