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, Journal Year: 2025, Volume and Issue: 438, P. 114014 - 114014

Published: April 6, 2025

Language: 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, Journal Year: 2025, Volume and Issue: 438, P. 114014 - 114014

Published: April 6, 2025

Language: Английский

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