Effects of spark plasma sintering parameters on mechanical and thermal properties of U3Si2 pellets

被引：0

作者：

Zou J. ^{[1
,3
]}

Xu S. ^{[1
,3
]}

Wang P. ^{[1
]}

Cao C. ^{[1
]}

Yan C. ^{[1
]}

Zhu Z. ^{[1
]}

Lin J. ^{[1
]}

You Y. ^{[2
]}

Lu J. ^{[2
]}

Zhu L. ^{[2
]}

机构：

[1] Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai

[2] Shanghai Nuclear Engineering Research and Design Institute Co., Ltd., Shanghai

[3] University of Chinese Academy of Sciences, Beijing

来源：

He Jishu/Nuclear Techniques | 2024年 / 47卷 / 02期

基金：

上海市自然科学基金;

关键词：

Accident-tolerant fuel; Mechanical properties; Spark plasma sintering; Thermal properties; U[!sub]3[!/sub]Si[!sub]2[!/sub;

D O I：

10.11889/j.0253-3219.2024.hjs.47.020605

中图分类号：

学科分类号：

摘要：

[Background] U3Si2 is regarded as one of the most promising accident-tolerant nuclear fuels for light water reactors and is expected to replace the UO2 nuclear fuel in the future. Currently, spark plasma sintering (SPS) is an advanced technique for preparing U3Si2 pellets; however, the influence of SPS parameters on the performance of the pellets is unclear. [Purpose] This study aims to investigate the effects of different sintering parameters (temperature and pressure) on the mechanical and thermal properties of the U3Si2 pellets prepared using SPS technology. [Methods] The thermal diffusivity of U3Si2 pellets was measured using a laser flash apparatus, and the thermal conductivity of the pellets was calculated. The mechanical properties of the pellets, including hardness, Young's modulus, and fracture toughness, were measured using nanoindenter. Thereafter, the influence of different sintering temperatures in the range of 1 000~1 300 ℃ and pressures in the range of 30~90 MPa on the mechanical and thermal properties of U3Si2 pellets were carefully examined. [Results] The measurement results show that the thermal conductivity of the as-synthesized pellets increases linearly with temperature in the range 27~700 ℃ . Moreover, increasing the sintering temperature and pressure improves the thermal conductivity of the U3Si2 pellets. The hardness and Young's modulus of the pellets increase with an increase in sintering temperature. They also exhibit a trend of first increasing and then stabilizing with increasing pressure, and tend to fully stabilize at 60 MPa. Moreover, the fracture toughness of the pellets decreases with the increase of sintering temperature and increases with increasing pressure. [Conclusions] Based on the above results, optimized SPS parameters for the U3Si2 pellets are proposed, and this study provides a reference for the preparation of high-performance U3Si2 pellets. © 2024 Science Press. All rights reserved.

引用

共 32 条

[1] Zhou W, Zhou W Z., Enhanced thermal conductivity accident tolerant fuels for improved reactor safety - a comprehensive review[J], Annals of Nuclear Energy, 119, pp. 66-86, (2018)
[2] Parker S S, White J T, Hosemann P, Et al., Thermophysical properties of thorium mononitride from 298 to 1700 K, Journal of Nuclear Materials, 526, (2019)
[3] Zinkle S J, Was G S., Materials challenges in nuclear energy[J], Acta Materialia, 61, 3, pp. 735-758, (2013)
[4] Katoh Y, Snead L L., Silicon carbide and its composites for nuclear applications - Historical overview, Journal of Nuclear Materials, 526, (2019)
[5] Metzger K E, Knight T W, Roberts E, Et al., Determination of mechanical behavior of U3Si2 nuclear fuel by microindentation method[J], Progress in Nuclear Energy, 99, pp. 147-154, (2017)
[6] Zinkle S J, Terrani K A, Gehin J C, Et al., Accident tolerant fuels for LWRs: a perspective[J], Journal of Nuclear Materials, 448, 1 – 3, pp. 374-379, (2014)
[7] Johnson K D, Raftery A M, Lopes D A, Et al., Fabrication and microstructural analysis of UN-U3Si2 composites for accident tolerant fuel applications, Journal of Nuclear Materials, 477, pp. 18-23, (2016)
[8] Ortega L H, Blamer B J, Evans J A, Et al., Development of an accident-tolerant fuel composite from uranium mononitride (UN) and uranium sesquisilicide (U3Si2) with increased uranium loading[J], Journal of Nuclear Materials, 471, pp. 116-121, (2016)
[9] ZHANG Haiqing, LU Linyuan, WANG Peng, Et al., Evaluation of influence of fault tolerant fuel structure on thermal conductivity, Nuclear Techniques, 44, 3, (2021)
[10] Harp J M, Lessing P A, Hoggan R E., Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation[J], Journal of Nuclear Materials, 466, pp. 728-738, (2015)

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