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

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...

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Bibliographic Details
Main Authors: He Yuan, Guan Wang, Rui Yu, Yujie Tao, Zhaohao Wang, Shaoqiang Guo, Wenbo Liu, Di Yun, Long Gu
Format: Article
Language:English
Published: Frontiers Media S.A. 2021-07-01
Series:Frontiers in Energy Research
Subjects:
UN fuel
annular fuel
fuel performance analysis
COMSOL
fast reactors
Online Access:https://www.frontiersin.org/articles/10.3389/fenrg.2021.705944/full

Internet

https://www.frontiersin.org/articles/10.3389/fenrg.2021.705944/full

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