真空烧结U<sub>3</sub>Si<sub>2</sub>燃料芯块的微观组织与导热性能

doi:10.19976/j.cnki.43-1448/TF.2022064

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Abstract Using U₃Si₂ powder as raw material, U₃Si₂ fuel pellets were prepared by vacuum sintering method. The effect of sintering temperature on the density of U₃Si₂ pellets was studied. The uranium concentration and impurity content of U₃Si₂ fuel pellets were also revealed. The microstructure and thermal conductivity property of U₃Si₂ fuel pellets were then characterized. The results show that the density of U₃Si₂ fuel pellets first increases and then decreases with the increase of sintering temperature. The U₃Si₂ fuel pellets sintered at 1 550 ℃ for 2 h possesses the highest relative density, which is about 96.7%. And the uranium mass concentration of the pellets is 10.81 g/cm³, significantly higher than the uranium mass concentration of the active UO₂ pellets. The U₃Si₂ fuel pellet is composed of U₃Si₂, USi and UO₂ phases. The thermal diffusivity of the pellet increases gradually with the increase of temperature. The thermal diffusivity at 500 ℃ is 3.95 mm²/s, which is about two times higher than that of the UO₂ pellet.

Key words： U₃Si₂fuel pellets accident tolerant fuel (ATF) powder metallurgy high uranium density fuel thermal conductivity

Received: 05 May 2022 Published: 14 September 2022

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	Articles by authors
	LU Yonghong
	JIA Daikun
	SU Danke
	PAN Xiaoqiang
	XIA Jibin
	WANG Yifan
	WANG Ting
	ZHANG Xiang
	WANG Zizhen
	QIUShaoyu

Cite this article:

LU Yonghong,JIA Daikun,SU Danke, et al. Microstructure and thermal conductivity property of U₃Si₂fuel pellets by vacuum sintering[J]. Materials Science and Engineering of Powder Metallurgy, 2022, 27(4): 436-441.

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http://pmbjb.csu.edu.cn/EN/10.19976/j.cnki.43-1448/TF.2022064 OR http://pmbjb.csu.edu.cn/EN/Y2022/V27/I4/436

[1] 徐銤. 加快核电发展, 有效降低碳排放[J]. 科技导报, 2017, 35(13): 1-1.
XU Mi.Accelerate the development of nuclear power and effectively reduce carbon emissions[J]. Science & Technology Review, 2017, 35(13): 3-3.
[2] 唐传宝, 柴晓明. 实现“双碳”目标, 核能不可或缺[J]. 中国机关后勤, 2022(1): 72-74.
TANG Chuanbao, CHAI Xiaoming.To achieve the carbon peaking and carbon neutrality goal, nuclear energy is indispensable[J]. Chinese Government General Services, 2022(1): 72-74.
[3] 莫华均, 张伟, 吴璐, 等. 耐事故UO₂ 基复合燃料芯块的研发进展[J]. 核动力工程, 2020, 41(2): 36-39.
MO Huajun, ZHANG Wei, WU Lu, et al.Progress of accident-tolerant UO₂-based composite fuel pellets[J]. Nuclear Power Engineering, 2020, 41(2): 36-39.
[4] 周军, 邱绍宇, 杜沛南, 等. 耐事故燃料包壳用FeCrAl不锈钢的研究进展[J]. 材料导报, 2017, 31(S2): 47-51.
ZHOU Jun, QIU Shaoyu, DU Peinan, et al.Research progress in the FeCrAl alloys for accident tolerant fuel cladding[J]. Materials Reports, 2017, 31(S2): 47-51.
[5] JASON M H, PAUL A L, RITA EH.Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation[J]. Journal of Nuclear Materials, 2015, 466:728-738.
[6] WHITE J T, NELSON A T, DUNWOODY J T, et al.Thermophysical properties of U₃Si₂ to 1 773 K[J]. Journal of Nuclear Materials , 2015, 464: 275-280.
[7] AFIQA M, YUJI O, HIROAKI M, et al.Thermal and mechanical properties of polycrystalline U₃Si₂ synthesized by spark plasmasintering[J]. Journal of Nuclear Science and Technology, 2018, 51(10): 12-22.
[8] DENISE A L, ANNA B, SIMON M, et al.Spark plasma sintering and microstructural analysis of pure and Modoped U₃Si₂ pellets[J]. Journal of Nuclear Materials, 2017, 496: 234-241.
[9] RITA E H, JASON M H, HE L F.Evaluation of U₃Si₂ fuel pellets sintered in an argon vs. vacuum environment[J]. Advances in Ceramics for Environmental, Functional, Structural, and Energy Applications: Ceramic Transactions, 2018, 265: 21-26.
[10] 张翔, 刘桂良, 刘云明, 等. U₃Si₂燃料芯块的制备与显微组织研究[J].核动力工程, 2019, 40(1): 56-59.
ZHANG Xiang, LIU Guiliang, LIU Yunming, et al.Study on fabrication and microstructural analysis of U₃Si₂fuel pellets[J]. Nuclear Power Engineering, 2019, 40(1): 56-59.
[11] ANTONIO D J, SHRESEHA K, HAPP J M, et al.Thermal and transport properties of U₃Si₂[J]. Journal of Nuclear Materials, 2018, 508: 154-158.
[12] NELSON A T, MIGDISOV A, WOOD E S, et al.U₃Si₂ behavior in H₂O environments: Part II pressurized water withcontrolled redox chemistry[J]. Journal of Nuclear Materials, 2018, 500: 81-91.
[13] RITA E H, KEVIN R T, FABIOLA C, et al.Grain size and phase purity characterization of U₃Si₂ fuelpellets[J]. Journal of Nuclear Materials, 2018, 512: 199-213.
[14] GUO X F, WHITE J T, NELSON A T, et al.Enthalpy of formation of U₃Si₂: a high-temperature drop calorimetry study[J]. Journal of Nuclear Materials, 2018, 507: 44-49.
[15] YAO T K, GONG B W, HE L F, et al.In-situ TEM study of the ion irradiation behavior of U₃Si₂ and U₃Si₅[J]. Journal of Nuclear Materials, 2018, 511: 56-63.
[16] FABIOLA C, JASON M H.Post-irradiation examinations of low burnup U₃Si₂ fuel for light water reactor applications[J]. Journal of Nuclear Materials, 2019, 518: 62-79.
[17] 孙明辉, 徐越, 王雪婷, 等. (Sr_1-3_x_/2Lax)TiO₃(x=0.2~0.5)陶瓷的显微组织结构及微波介电性能研究[J]. 齐鲁工业大学学报, 2018, 32(6): 7-12.
SUN Minghui, XU Yue, WANG Xueting, et al.Crystal microstructure and microwave dielectric properties of(Sr_1-3_x_/2Lax)TiO₃(x=0.2~0.5) ceramics[J]. Journal of QILU University of Technology, 2018, 32(6): 7-12.
[18] 高旭芳, 丘泰. Bi掺杂对Ba_6-3_xLa₈₊₂_x(Ti_0.95Zr_0.05)₁₈O₅₄(x=2/3)陶瓷的烧结性能和介电性能的影响[J]. 中国有色金属学报, 2010, 20(3): 529-533.
GAO Xufang, QIU Tai.Effects of Bi doping on sintering and dielectric characteristics of Ba_6-3_xLa₈₊₂_x(Ti_0.95Zr_0.05)₁₈O₅₄(x=2/3) ceramics[J]. The Chinese Journal of Nonferrous Metals, 2010, 20(3): 529-533.
[19] MUTSUMI H.Thermal diffusivity of UO₂-Gd₂O₃ pellets[J]. Journal of Nuclear Materials, 1990, 173: 247-254.