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Articles

Original Research

Published on 27 Jul 2021

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

in Nuclear Energy

He Yuan
Guan Wang
Rui Yu
Yujie Tao
Zhaohao Wang
Shaoqiang Guo
Wenbo Liu
Di Yun
Long Gu

Frontiers in Energy Research

doi 10.3389/fenrg.2021.705944

3,907 views
4 citations