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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...

Täydet tiedot

Tallennettuna:
Päätekijät: He Yuan, Guan Wang, Rui Yu, Yujie Tao, Zhaohao Wang, Shaoqiang Guo, Wenbo Liu, Di Yun, Long Gu
Aineistotyyppi: Artigo
Kieli:Inglês
Julkaistu: Frontiers Media S.A. 2021-07-01
Sarja:Frontiers in Energy Research
Aiheet:
UN fuel
annular fuel
fuel performance analysis
COMSOL
fast reactors
Linkit:https://www.frontiersin.org/articles/10.3389/fenrg.2021.705944/full
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