Chemical interaction layer between uranium oxide fuel pellet and zirconium alloy cladding in pressurized water reactor

BackgroundDuring reactor operation, zirconium (Zr) alloy cladding is continuously oxidized as it gets in contact with fuel, and combines with the fuel to form a firm chemical interaction layer. This affects the thermal conductivity of the fuel gap, the mechanical properties of the cladding, and the...

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Bibliographic Details

Published in:	Hé jìshū Vol. 46; no. 9; p. 090602
Main Authors:	WANG Huacai, YANG Dawei, CHENG Huanlin, TANG Qi, WANG Wei, QIAN Jin
Format:	Journal Article
Language:	Chinese
Published:	Science Press 01-09-2023
Subjects:	(u,zr)ox compound chemical adhesion chemical interaction layer intact fuel rod pressurized water reactor nuclear power plant
Online Access:	Get full text
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