Thorium and fully ceramic microencapsulated TRISO fuel neutronics feasibility analysis in a gas cooled fast reactor: Enhancing transmutation of long-lived fission products DOI

Shohanul Islam

Nuclear Engineering and Design, Год журнала: 2025, Номер 438, С. 114014 - 114014

Опубликована: Апрель 6, 2025

Язык: Английский

Thorium and fully ceramic microencapsulated TRISO fuel neutronics feasibility analysis in a gas cooled fast reactor: Enhancing transmutation of long-lived fission products DOI

Shohanul Islam

Nuclear Engineering and Design, Год журнала: 2025, Номер 438, С. 114014 - 114014

Опубликована: Апрель 6, 2025

Язык: Английский

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