Lead-Cooled Fast Reactor Annular UN Fuel Design and Development of Performance Analysis Program

A kind of annular uranium nitride (UN) fuel suitable for lead-cooled fast reactor applications has been designed in this study. The design is directly targeting two main issues of UN fuel: severe swelling and thermal decomposition of UN fuel at high temperatures. A performance analysis program based...

Ausführliche Beschreibung

Bibliografische Detailangaben

Hauptverfasser:	He Yuan, Guan Wang, Rui Yu, Yujie Tao, Zhaohao Wang, Shaoqiang Guo, Wenbo Liu, Di Yun, Long Gu
Format:	Artigo
Sprache:	Inglês
Veröffentlicht:	Frontiers Media S.A. 2021-07-01
Schriftenreihe:	Frontiers in Energy Research
Schlagworte:	UN fuel annular fuel fuel performance analysis COMSOL fast reactors
Online-Zugang:	https://www.frontiersin.org/articles/10.3389/fenrg.2021.705944/full
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