Fabrication and Microstructure Characterization of Porous U-10Zr Metallic Fuel Pellet

被引：0

作者：

Zhao R. ^{[1
]}

He J. ^{[1
]}

机构：

[1] China North Nuclear Fuel Company, Ltd., Baotou

来源：

Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2021年 / 55卷

关键词：

Microstructure; Porous material; U-10Zr metallic fuel;

D O I：

10.7538/yzk.2021.zhuankan.0187

中图分类号：

学科分类号：

摘要：

The U-10Zr metallic fuel is a significant alternative material for light water reactor, sodium cooled fast reactor, etc. In order to decrease the density of metallic fuel pellet and improve the dimensional stability under irradiation, a new porous metallic fuel was proposed, which contained a certain quantity of porosity for fission gas and volumetric expansion. The U-10Zr metallic fuel pellet was fabricated by cool-pressing moulding and solid-state sintering, and the relationship between sintering process and pellet density was researched. Then, the characterization for pellet performance was implemented, including microstructure, phase composition, etc. The results show that the density of sample pellet increases with the sintering time at the sintering temperature of 1 100℃, and the porosity can be controlled by adjusting the sintering time. © 2021, Editorial Board of Atomic Energy Science and Technology. All right reserved.

引用

页码：272 / 275

页数：3

共 5 条

[1] LI Zhenghong, HUANG Hongwen, WANG Zhen, Et al., Conceptual design of Z-pinch driven fusion-fission hybrid power reactor, High Power Laser and Particle Beams, 26, 10, pp. 1-7, (2014)
[2] WALTERS L, KITTEL J., Development and performance of metal fuel elements for fast breeder reactors, Nuclear Technology, 48, 3, pp. 273-280, (1980)
[3] BRAGG-SITTON S M., Development of advanced accident tolerant fuels for commercial light water reactors, Nuclear News, 57, pp. 83-91, (2014)
[4] HU Yun, XU Mi, Development of metallic fuel for fast reactor, Atomic Energy Science and Technology, 42, 9, pp. 810-815, (2008)
[5] BURKES D E, FIELDING R S, PORTER D L., Metallic fast reactor fuel fabrication for global nuclear energy partnership, Journal of Nuclear Materials, 392, 2, pp. 158-163, (2009)

← 1 →