核燃料裂变气体行为研究进展

doi:10.11896/cldb.22090311

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Abstract Fission gas behavior of nuclear fuels is one of the most critical factors affecting the performance of nuclear fuels. Fission gas mainly refers to the inert gas generated during fission process inside nuclear fuels, and these gases are relatively stable, insoluble in the fuel matrix, and mostly remain in the fuel in a gaseous state. Fission gas stored in the fuel material matrix will cause the fuel to swell, and the released fission gas will affect thermal conductivity of the gap between the fuel and cladding and internal pressure of the gas plenum, and either way these gases will threaten fuel safety. Therefore, it is of great significance to study fission gas behaviors.
So far, relevant research activities on the behaviors of fission gas have been carried out for more than 60 years, and researchers have obtained a profound understanding of the behaviors of fission gas, developed a complete set of fission gas behavior theories, including fission generation, bubble nucleation, bubble coalescence, bubble migration, gas atom resolution and fission gas release. Such theory has been widely used in the performance analysis of nuclear fuels, making great contributions to nuclear fuel design.
This paper summarizes various peculiar fission gas behaviors in the fission gas behavior theory, explains the causes and processes of each fission gas behavior in detail, introduces unique fission gas behaviors of different types of nuclear fuels, including empirical models and mechanistic models of different nuclear fuels, and finally, summarizes the focus of current fission gas behaviors research.

Key words： nuclear fuels fission gas behaviors ceramic fuel metallic fuel

Published: 25 January 2024 Online: 2024-01-26

CLC number:

TL352

Fund:Xi’an Jiaotong University CNNC Leading Innovation Fund in 2019 and 2020.

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	QIAN Zhengyu
	YAN Dong
	YUN Di

Cite this article:

QIAN Zhengyu,YAN Dong,YUN Di. Research Progress on Fission Gas Behavior of Nuclear Fuels[J]. Materials Reports, 2024, 38(2): 22090311-10.

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http://www.mater-rep.com/EN/10.11896/cldb.22090311 OR http://www.mater-rep.com/EN/Y2024/V38/I2/22090311

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