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| 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 |
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Cite this article:
WANG Mingjiang, WANG Xiaomin, XIAO Hongxing. Research Progress on Corrosion Resistance of UN Fuel and Its Doping Modification. Journal of Chinese Society for Corrosion and protection, 2026, 46(2): 352-364.
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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.
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Received: 25 May 2025
32134.14.1005.4537.2025.158
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| [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
|
|
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
|
|
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
|
|
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
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