Please wait a minute...
最新录用 | 当期目录 | 过刊浏览 | 热点文章 | 虚拟专辑 | 阅读排行 | 下载排行 | 引用排行 | 期刊订阅
中国腐蚀与防护学报  2026, Vol. 46 Issue (2): 352-364     CSTR: 32134.14.1005.4537.2025.158      DOI: 10.11902/1005.4537.2025.158
  综合评述 本期目录 | 过刊浏览 |
UN燃料耐腐蚀性能及掺杂改性的研究进展
王明江, 王晓敏(), 肖红星
中国核动力研究设计院核燃料元件及材料研究所 核反应堆技术全国重点实验室 成都 610213
Research Progress on Corrosion Resistance of UN Fuel and Its Doping Modification
WANG Mingjiang, WANG Xiaomin(), XIAO Hongxing
Key Laboratory of Nuclear Reactor Technology, Nuclear Fuel Element and Material Sub-institute of NPIC, Chengdu 610213, China
引用本文:

王明江, 王晓敏, 肖红星. UN燃料耐腐蚀性能及掺杂改性的研究进展[J]. 中国腐蚀与防护学报, 2026, 46(2): 352-364.
Mingjiang WANG, Xiaomin WANG, Hongxing XIAO. Research Progress on Corrosion Resistance of UN Fuel and Its Doping Modification[J]. Journal of Chinese Society for Corrosion and protection, 2026, 46(2): 352-364.

全文: PDF(5585 KB)   HTML
摘要: 

UN燃料因其具有高熔点、高铀密度、高热导率等特点，在提升反应堆安全性和经济性方面相比于UO2燃料具有显著优势，是事故容错燃料(ATF)耐事故燃料方案中具有较大发展潜力的新型高性能燃料之一。然而，UN燃料的耐水腐蚀性能较差。前期的研究表明，通过掺杂可在一定程度上改善UN燃料的耐腐蚀性能。目前已开展研究的掺杂相包括UO2、U3Si2、UB2、Zr、Cr、Al、Ni等，在提高腐蚀起始温度和降低腐蚀速率方面取得了一定的成效。本文较为全面地总结了UN燃料的腐蚀行为以及通过掺杂改善UN燃料耐腐蚀性能的研究进展，同时分析了现有研究存在的不足以及未来可行的改进方向，为进一步研究和提升UN燃料耐腐蚀性能提供参考。
关键词 ： UN燃料,  耐腐蚀性能,  制备工艺,  掺杂改性    
Abstract：

The UN fuel, characterized by its high melting point, high uranium density, and high thermal conductivity, demonstrates significant advantages over UO2 fuel in enhancing the safety and economy of reactors, making it one of the promising new high-performance fuels with great potential in the Accident Tolerant Fuel (ATF) program. However, the UN fuel exhibits poor resistance to hydrothermal corrosion. Previous studies have indicated that doping can improve the corrosion resistance of UN fuel to some extent. The doping substances that have been investigated include UO2, U3Si2, UB2, Zr, Cr, Al and Ni etc., which have achieved certain success in raising the initiation temperature of corrosion and reducing the corrosion rate of UN materials. This paper provides a comprehensive summary of the corrosion behavior of UN fuel and the research progress on improving the corrosion resistance of UN fuel through doping. Additionally, it analyzes the deficiencies in the present research and feasible directions for improvement, offering references for further research and enhancement of the corrosion resistance of UN fuel.
Key words： UN fuel    corrosion resistance    preparation process    doping
收稿日期: 2025-05-25      32134.14.1005.4537.2025.158
ZTFLH:  TL352  
通讯作者: 王晓敏，E-mail：npicwxm@163.com，研究方向为核燃料元件及材料研究
作者简介: 王明江，男，2000年生，硕士生
服务
把本文推荐给朋友
加入引用管理器
E-mail Alert
RSS
作者相关文章
王明江
王晓敏
肖红星

链接本文:

https://www.jcscp.org/CN/10.11902/1005.4537.2025.158      或      https://www.jcscp.org/CN/Y2026/V46/I2/352

图1  UN芯块腐蚀后的微观结构[11]
图2  UN、U2N3和UO2样品厚度随H2O2暴露时间的变化[12]
图3  UN (110)表面上H2O解离反应的势能变化[15]和氧原子的迁移路径[17]
图4  密度、杂质含量和H2对UN腐蚀增重的影响[20]
Preparation processPurityDensityGrain sizeCorrosion resistance
HDNHigh--Higher purity is beneficial for enhancing corrosion resistance
CTR-NHigh carbon and oxygen content--Both carbon and oxygen impurities will reduce the corrosion resistance
HP-A higher sintering temperature may cause the UN to decom-pose and result in a decrease in densityRelated to the ball-milling method and the ball-mill-ing time; relatively smallerAffected by density and grain size, the influence of other microstructures still needs to be studied
SPS-It is conducive to increasing densityRelated to the ball-milling method and the ball-mill-ing time; relatively largerHigher density and smaller grain size are conducive to enhancing corrosion resistance. the influence of other microstructures still needs to be explored
表1  制备工艺对UN燃料芯块特性的影响
图5  放电等离子烧结(SPS)的芯块相对密度与温度、压力的关系[31]
Preparation parametersGrain size / μmOnset temperature / ℃Oxidation rate / %·min-1
1500-80-298.60.35
1700-410-60377.60.44
1600-8010378.60.45
1550-1000.6381.80.14
1550-808401.30.35
1600-4428420.30.43
表2  不同制备参数的UN燃料样品的氧化起始温度[32]
图6  UN和UN-UO2在不同温度水中腐蚀30 min后的形貌[36]
图7  UN和UN-UO2腐蚀过程中反应分数α与温度的关系[13]
图8  UN和UN-U3Si2的氧化增重曲线[44]及UN-U3Si2腐蚀30 min (300 ℃，9 MPa)后的微观结构[11]
图9  UN-UB2和UN腐蚀后的形貌[47]
图10  UN-ZrN的微观结构[49]，UN和UN-ZrN的氧化增重曲线[49]，UN和U0.77Zr0.23N在蒸汽中的腐蚀速率[50]及Arrhenius曲线[50]
图11  金属和O元素的晶界偏析能与强化能[53]
图12  UN及复合燃料芯块的增重曲线[56]
AdditiveFormInfluenceConclusion
UO2Dual-phaseThe onset temperature decreases and the corrosion rate acceleratesThe doping of UO2 will cause corrosion to occur throughout the entire core block, providing more diffusion channels and intensifying the corrosion of the fuel
U3Si2Dual-phaseThe onset temperature rises, and the corrosion rate accelerates in the later stage. The weight gain decreases within a short period of timeThe doping of U3Si2 transforms the corrosion mechanism into intergranular corrosion, thereby inhibiting crack propagation
UB2Partial solid solutionThe onset temperature increased while the corrosion rate remained basically the same, and the integrity after corrosion was betterThe UB2 at the grain boundaries may have inhibited the occurrence of corrosion through the grain boundary modification method, and enhanced the integrity after corrosion
ZrComplete solid solutionThe onset temperature and corrosion rate vary depending on the experimental methodThe sensitivity of solid solutions to air and steam may vary
Al、NiDual-phaseThe sintering process is difficult. The addition of Al will lower the initial temperatureThe differences between the UN and Al in terms of density and thermal expansion coefficient result in significant internal stress, which further aggravates the corrosion
CrPartial solid solutionThe initial temperature rises, and it further increases after annealingSolid solutions play a significant role in enhancing corrosion resistance. The effects of suppressing segregation and increasing the strength of grain boundaryneed to be further verified
表3  掺杂物对UN燃料耐腐蚀性能的影响汇总
[1] Goldner F. Development strategy for advanced LWR fuels with enhanced accident tolerance [R]. USDOE Office of Nuclear Energy, 2012
[2] Watkins J K, Gonzales A, Wagner A R, et al. Challenges and opportunities to alloyed and composite fuel architectures to mitigate high uranium density fuel oxidation: Uranium mononitride [J]. J. Nucl. Mater., 2021, 553: 153048
[3] Matthews R B. Irradiation performance of nitride fuels [R]. Los Alamos, NM, USA: Los Alamos National Laboratory, 1993
[4] Pastore G, Toptan A. Fresh fuel properties: Ceramic compounds [J]. Encycl. Nucl. Energy, 2021: 343
[5] Zakova J, Wallenius J. Fuel residence time in BWRs with nitride fuels [J]. Ann. Nucl. Energy, 2012, 47: 182
[6] Youinou G J, Sen R S. Impact of accident-tolerant fuels and claddings on the overall fuel cycle: A preliminary systems analysis [J]. Nucl. Energy, 2014, 188: 123
[7] Chen X Y, Ding Y, Ding J, et al. Research progress and development trend of accident tolerant fuel UN pellets [J]. Nucl. Power Eng., 2024, 45(suppl.1): 130
[7] 陈向阳, 丁 阳, 丁 捷 等. 耐事故燃料UN芯块研究进展和发展趋势 [J]. 核动力工程, 2024, 45(): 130
[8] Dell R M, Wheeler V J, Bridger N J. Hydrolysis of uranium mononitride [J]. Trans. Faraday Soc., 1967, 63: 1286
[9] Sunder S, Miller N H. XPS and XRD studies of corrosion of uranium nitride by water [J]. J. Alloy. Compd., 1998, 271-273: 568
[10] Jolkkonen M, Malkki P, Johnson K, et al. Uranium nitride fuels in superheated steam [J]. J. Nucl. Sci. Technol., 2017, 54: 513
[11] Lopes D A, Uygur S, Johnson K. Degradation of UN and UN-U3Si2 pellets in steam environment [J]. J. Nucl. Sci. Technol., 2017, 54: 405
[12] Lawrence Bright E, Rennie S, Siberry A, et al. Comparing the corrosion of uranium nitride and uranium dioxide surfaces with H2O2 [J]. J. Nucl. Mater., 2019, 518: 202
[13] Rao G A R, Mukerjee S K, Vaidya V N, et al. Oxidation and hydrolysis kinetic studies on UN [J]. J. Nucl. Mater., 1991, 185: 231
[14] Bo T, Lan J H, Zhang Y J, et al. Adsorption and dissociation of H2O on the (001) surface of uranium mononitride: Energetics and mechanism from first-principles investigation [J]. Phys. Chem. Chem. Phys., 2016, 18: 13255
[15] Bo T, Lan J H, Zhao Y L, et al. First-principles study of water reacting with the (110) surface of uranium mononitride [J]. J. Nucl. Mater., 2017, 492: 244
[16] Sikorski E L, da Silva T H, Aagesen L K, et al. First-principles comparative study of UN and Zr corrosion [J]. J. Nucl. Mater., 2019, 523: 402
[17] Bocharov D, Gryaznov D, Zhukovskii Y F, et al. Ab initio simulations of oxygen interaction with surfaces and interfaces in uranium mononitride [J]. J. Nucl. Mater., 2013, 435: 102
[18] Lawrence Bright E, Darnbrough J E, Goddard D T, et al. Oxidation and passivation of the uranium nitride (001) surface [J]. Corros. Sci., 2022, 209: 110705
[19] Liu J T, Gasparrini C, White J T, et al. Thermal expansion and steam oxidation of uranium mononitride analysed via in situ neutron diffraction [J]. J. Nucl. Mater., 2023, 575: 154215
[20] Sooby E S, Brigham B A, Robles G, et al. Steam oxidation of uranium mononitride in pure and reducing steam atmospheres to 1200 ℃ [J]. J. Nucl. Mater., 2022, 560: 153487
[21] Sugihara S, Imoto S. Hydrolysis of uranium nitrides [J]. J. Nucl. Sci. Technol., 1969, 6: 237
[22] Scott T B, Petherbridge J R, Harker N J, et al. The oxidative corrosion of carbide inclusions at the surface of uranium metal during exposure to water vapour [J]. J. Hazard. Mater., 2011, 195: 115
[23] Ekberg C, Ribeiro Costa D, Hedberg M, et al. Nitride fuel for Gen IV nuclear power systems [J]. J. Radioanal. Nucl. Chem., 2018, 318: 1713
[24] Li Z S, Shao Z Y, Liu W T, et al. Preparation technology of uranium nitride fuel powder and pellet [J]. At. Energy Sci. Technol., 2021, 55(suppl.2): 276
[24] 李宗书, 邵宗义, 刘文涛 等. 氮化铀燃料粉末及芯块制备技术研究 [J]. 原子能科学技术, 2021, 55(): 276
[25] Mukerjee S K, Dehadraya J V, Vaidya V N, et al. Kinetics of the carbothermic synthesis of uranium mononitride microspheres [J]. J. Nucl. Mater., 1991, 185: 39
[26] Matthews R B, Chidester K M, Hoth C W, et al. Fabrication and testing of uranium nitride fuel for space power reactors [J]. J. Nucl. Mater., 1988, 151: 345
[27] Yin B Y, Qu Z H. Property of uranium nitride ceramic pellet by hot press sintering [J]. At. Energy Sci. Technol., 2014, 48: 1850
[27] 尹邦跃, 屈哲昊. 热压烧结UN陶瓷芯块的性能 [J]. 原子能科学技术, 2014, 48: 1850
[28] Munir Z A, Anselmi-Tamburini U, Ohyanagi M. The effect of electric field and pressure on the synthesis and consolidation of materials: A review of the spark plasma sintering method [J]. J. Mater. Sci., 2006, 41: 763
[29] Muta H, Kurosaki K, Uno M, et al. Thermal and mechanical properties of uranium nitride prepared by SPS technique [J]. J. Mater. Sci., 2008, 43: 6429
[30] Malkki P, Jolkkonen M, Hollmer T, et al. Manufacture of fully dense uranium nitride pellets using hydride derived powders with spark plasma sintering [J]. J. Nucl. Mater., 2014, 452: 548
[31] Johnson K D, Wallenius J, Jolkkonen M, et al. Spark plasma sintering and porosity studies of uranium nitride [J]. J. Nucl. Mater., 2016, 473: 13
[32] Yang K, Kardoulaki E, Zhao D, et al. Uranium nitride (UN) pellets with controllable microstructure and phase-fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties [J]. J. Nucl. Mater., 2021, 557: 153272
[33] Gonzales A, Watkins J K, Wagner A R, et al. Challenges and opportunities to alloyed and composite fuel architectures to mitigate high uranium density fuel oxidation: uranium silicide [J]. J. Nucl. Mater., 2021, 553: 153026
[34] Lessing P A. Oxidation protection of uranium nitride fuel using liquid phase sintering [R]. Idaho Falls, ID, USA: Idaho National Lab. (INL), 2012
[35] Jaques B J, Watkins J, Croteau J R, et al. Synthesis and sintering of UN-UO2 fuel composites [J]. J. Nucl. Mater., 2015, 466: 745
[36] Watkins J K, Butt D P, Jaques B J. Microstructural degradation of UN and UN-UO2 composites in hydrothermal oxidation conditions [J]. J. Nucl. Mater., 2019, 518: 30
[37] Yang J H, Kim D S, Kim D J, et al. Oxidation and phase separation of U3Si2 nuclear fuel in high-temperature steam environments [J]. J. Nucl. Mater., 2020, 542: 152517
[38] Wood E S, White J T, Grote C J, et al. U3Si2 behavior in H2O: Part I, flowing steam and the effect of hydrogen [J]. J. Nucl. Mater., 2018, 501: 404
[39] Johnson K D, Raftery A M, Lopes D A, et al. Fabrication and microstructural analysis of UN-U3Si2 composites for accident tolerant fuel applications [J]. J. Nucl. Mater., 2016, 477: 18
[40] 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]. J. Nucl. Mater., 2016, 471: 116
[41] White J T, Travis A W, Dunwoody J T, et al. Fabrication and thermophysical property characterization of UN/U3Si2 composite fuel forms [J]. J. Nucl. Mater., 2017, 495: 463
[42] Lopes D A, Wilson T L, Kocevski V, et al. Experimental and computational assessment of U-Si-N ternary phases [J]. J. Nucl. Mater., 2019, 516: 194
[43] Uygur S. Degradation mechanisms of UN and UN-10U3Si2 pellets of varying microstructure by comparative steam oxidation experiments [D]. Stockholm: KTH Royal Institute of Technology, 2016
[44] Johnson K, Ström V, Wallenius J, et al. Oxidation of accident tolerant fuel candidates [J]. J. Nucl. Sci. Technol., 2016, 54: 1
[45] Turner J, Abram T. Steam performance of UB2/U3Si2 composite fuel pellets, compared to U3Si2 reference behaviour [J]. J. Nucl. Mater., 2020, 529: 151919
[46] Turner J, Buckley J, Worth R N, et al. UN-UB2 composite fuel material; improved water tolerance with integral burnable absorber [J]. J. Nucl. Mater., 2022, 559: 153471
[47] Pritchard M J, Buckley J, Abram T J, et al. Development of high-temperature-steam resistant UN via the addition of UB2 [J]. J. Nucl. Mater., 2025, 603: 155398
[48] Yang S B, Gao W H, Zheng J Y, et al. Atomic-scale insights into oxidation of Zr- and Y-doped UN surfaces and grain boundaries in steam: A first-principles study [J]. Surf. Interfaces, 2025, 65: 106490
[49] Mishchenko Y, Patnaik S, Wallenius J, et al. Thermophysical properties and oxidation behaviour of the U0.8Zr0.2N solid solution [J]. Nucl. Mater. Energy, 2023, 35: 101459
[50] Stansby J H, Mishchenko Y, Patnaik S, et al. Enhanced steam oxidation resistance of uranium nitride nuclear fuel pellets [J]. Corros. Sci., 2024, 230: 111877
[51] Malkki P. The manufacturing of uranium nitride for possible use in light water reactors [D]. Stockholm: KTH Royal Institute of Technology, 2015
[52] Gong B W, Cai L, Lei P H, et al. Cr-doped U3Si2 composite fuels under steam corrosion [J]. Corros. Sci., 2020, 177: 109001
[53] Wang Y Y, Zhao J J, Jiang Y H, et al. Oxidation susceptibility of UN Σ5 (210) grain boundary with Al/Cr/Ni dopant: A first-principles study [J]. J. Nucl. Mater., 2023, 578: 154344
[54] Herman A, Ekberg C. A uranium nitride doped with chromium, nickel or aluminum as an accident tolerant fuel [J]. Res. Rev.: J. Mater. Sci., 2017, 5: 83
[55] Insulander Björk K, Herman A, Hedberg M, et al. Scoping studies of dopants for stabilization of uranium nitride fuel [J]. Nucl. Sci. Eng., 2019, 193: 1255
[56] Mishchenko Y, Johnson K D, Jädernäs D, et al. Uranium nitride advanced fuel: An evaluation of the oxidation resistance of coated and doped grains [J]. J. Nucl. Mater., 2021, 556: 153249
[57] Mishchenko Y, Johnson K D, Wallenius J, et al. Design and fabrication of UN composites: from first principles to pellet production [J]. J. Nucl. Mater., 2021, 553: 153047
[58] Yang K, Kardoulaki E, Zhao D, et al. Cr-incorporated uranium nitride composite fuels with enhanced mechanical performance and oxidation resistance [J]. J. Nucl. Mater., 2022, 559: 153486
[1] 严建成, 冯向东, 卢得勇, 李进, 孟鹏军, 娄宝辉, 郭健, 李正涛, 朱正旺. 一种Cu-Zn基高熵合金在硬水中的腐蚀行为研究[J]. 中国腐蚀与防护学报, 2026, 46(2): 601-610.
[2] 周丽, 曹晓蝶, 来佑彬, 丁旺旺, 韦博鑫, 吴嘉俊. 热处理工艺对增材制造金属零件腐蚀行为影响的研究进展[J]. 中国腐蚀与防护学报, 2026, 46(1): 37-48.
[3] 苏宝献, 高如心, 朱国强, 姜博涛, 王斌斌, 刘琛, 于永生, 王亮, 苏彦庆. 热处理工艺对电子束熔丝沉积Ti-6Al-3Nb-2Zr-1Mo合金微观组织与腐蚀行为的影响[J]. 中国腐蚀与防护学报, 2026, 46(1): 81-91.
[4] 李茂, 邓轲, 陈衍祥, 刘中豪, 李尚, 郭宇婷, 董选普, 曹华堂. N2 流量和靶基距对多弧离子镀沉积AlSiN纳米复合涂层的微观组织及耐腐蚀性能影响[J]. 中国腐蚀与防护学报, 2025, 45(4): 1041-1050.
[5] 冉仁豪, 单慧琳, 张鹏杰, 汪冬梅, 斯佳佳, 徐光青, 吕珺. 表层镁合金化NdFeB磁体的制备及其耐腐蚀性能[J]. 中国腐蚀与防护学报, 2025, 45(4): 1117-1126.
[6] 赵立佳, 崔新宇, 王吉强, 熊天英. 冷喷涂B4C/Al复合涂层在硼酸溶液中的腐蚀行为[J]. 中国腐蚀与防护学报, 2025, 45(1): 164-172.
[7] 李红玲, 郎五可. 环境友好防腐材料-聚苯胺纳米复合材料的制备及其研究进展[J]. 中国腐蚀与防护学报, 2024, 44(4): 874-882.
[8] 林一, 刘涛, 郭彦兵, 阮晴, 郭章伟, 董丽华. 船用低温钢焊接材料的研发与腐蚀方法评价[J]. 中国腐蚀与防护学报, 2024, 44(4): 957-964.
[9] 耿真真, 张钰柱, 杜小将, 吴汉辉. S2- 和Cl- 对316L奥氏体不锈钢的腐蚀钝化行为的协同作用[J]. 中国腐蚀与防护学报, 2024, 44(3): 797-806.
[10] 丁立, 邹文杰, 张雪姣, 陈均. ADC12铝合金表面硅锆复合转化膜的研究[J]. 中国腐蚀与防护学报, 2023, 43(4): 903-910.
[11] 胡雄鑫, 张弦, 刘静, 吴开明, 林安. 无取向电工钢用磷酸盐系绝缘环保涂层的研制及性能研究[J]. 中国腐蚀与防护学报, 2022, 42(5): 805-812.
[12] 张赪栋, 刘斌, 石泽耀, 刘岩, 曹青敏, 蹇冬辉. 镍铝青铜合金海水腐蚀行为研究进展[J]. 中国腐蚀与防护学报, 2022, 42(1): 25-33.
[13] 冯彦朋, 张弦, 吴开明, 杨淼. 热处理工艺对超细贝氏体钢显微组织及耐腐蚀性能的影响[J]. 中国腐蚀与防护学报, 2021, 41(5): 602-608.
[14] 王晓鸽, 高克玮, 颜鲁春, 杨会生, 庞晓露. Ce对镁合金表面ZnAlCe-LDHs薄膜耐腐蚀性能的影响机理研究[J]. 中国腐蚀与防护学报, 2021, 41(3): 335-340.
[15] 史昆玉, 吴伟进, 张毅, 万毅, 于传浩. TC4表面沉积Nb涂层在模拟体液环境下的电化学性能研究[J]. 中国腐蚀与防护学报, 2021, 41(1): 71-79.

版权所有 © 2017 《中国腐蚀与防护学报》编辑部　
地址: 沈阳市文化路72号, 中国科学院金属研究所(110016)
电话: +86-024-23971318，024-23971819　E-mail: jcscp@imr.ac.cn
本系统由北京玛格泰克科技发展有限公司设计开发 技术支持：support@magtech.com.cn