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Graphite flakes/UO2 fuel pellets with excellent thermal conductivity in radial direction.

Authors :
Li, Bingqing
Yang, Zhenliang
Wang, Zhiyi
Huang, Qiqi
Liu, Xuxu
Yan, Biaojie
Cheng, Liang
Shi, Tao
Zhang, Dezhi
Wu, Min
Gao, Rui
Chu, Mingfu
Zhang, Pengcheng
Bai, Bin
Source :
Journal of Nuclear Materials. Mar2021, Vol. 545, pN.PAG-N.PAG. 1p.
Publication Year :
2021

Abstract

• Graphite flakes were used to improve the radial thermal conductivity of UO 2. • Graphite flakes/UO 2 presented highly-oriented structure and well-bonded interface. • The radial thermal conductivity of graphite flakes/UO 2 was greatly improved by ~200%. In order to increase the radial thermal conductivity (TC) of UO 2 pellets, highly-oriented graphite flakes (GFs) were first introduced to UO 2 pellets by spark plasma sintering. The radial TC of GFs/UO 2 agreed well with Hatta-Taya model, which was closely related to the well-bonded interface and highly-oriented structure. Compared with UO 2 , the radial TC of GFs/UO 2 was greatly improved by about 200 % within a wide temperature range, higher than all the other reported value until now. Such enhancement in TC would significantly improve the safety of UO 2 fuel pellets. [ABSTRACT FROM AUTHOR]

Details

Language :
English
ISSN :
00223115
Volume :
545
Database :
Academic Search Index
Journal :
Journal of Nuclear Materials
Publication Type :
Academic Journal
Accession number :
148335506
Full Text :
https://doi.org/10.1016/j.jnucmat.2020.152639