U-50Zr合金在核燃料领域的性能与应用潜力研究

王兴栋; 易致豪; 田浩; 邓麒林; 史晓龙; 胡红军

doi:10.3969/j.issn.1674-6457.2026.06.022

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精密成形工程 ›› 2026, Vol. 18 ›› Issue (6) : 260-274. DOI: 10.3969/j.issn.1674-6457.2026.06.022

难熔金属成形

U-50Zr合金在核燃料领域的性能与应用潜力研究

王兴栋, 易致豪, 田浩, 邓麒林, 史晓龙, 胡红军^*

作者信息 +

Performance and Application Potential of U-50Zr Alloy in Nuclear Fuel

WANG Xingdong, YI Zhihao, TIAN Hao, DENG Qilin, SHI Xiaolong, HU Hongjun^*

Author information +

文章历史 +

摘要

随着核能技术的快速发展,对高性能核燃料材料的需求日益迫切。为应对核能发展对高性能燃料的迫切需求,以及克服传统UO₂燃料热导率低的固有缺陷,开发具有优异热物理性能的金属燃料至关重要。U-50Zr合金,以其独特的δ-UZr₂稳定相结构,展现出作为先进核燃料材料的巨大潜力。本文综述了该合金的制备方法、微观组织结构、力学性能以及热物理性能等方面的最新研究成果。重点聚焦其在轻水反应堆（LWR）事故容错燃料（ATF）中的应用场景,系统分析了不同制备工艺的优劣、性能影响因素及辐照行为特征,并与主流核燃料材料进行对比。研究表明,U-50Zr合金具有优异的热导率和较低的辐照肿胀率,能够在高温下保持良好的力学性能,显示出在轻水反应堆（LWR）燃料等应用中的巨大潜力。同时,合金的微观结构稳定性和相变行为对其性能具有重要影响,通过热处理和辐照处理可进一步优化其性能。此外,本文还探讨了合金与包壳材料的结合效果及影响因素,以及在实际反应堆中的辐照稳定性和安全性。综合现有研究,本文认为U-50Zr合金在核燃料领域具有广阔的应用前景,但仍需深入研究以克服现有挑战并实现广泛应用。

Abstract

With the rapid development of nuclear energy technology, the demand for high-performance nuclear fuel materials is becoming increasingly urgent. To meet the urgent demand for high-performance fuel in the development of nuclear energy and to overcome the inherent defect of low thermal conductivity of traditional UO₂ fuel, it is crucial to develop metal fuels with excellent thermal physical properties. The U-50Zr alloy, with its unique δ-UZr₂ stable phase structure, shows great potential as an advanced nuclear fuel material. The work aims to review the latest research results on the preparation methods, microstructure, mechanical properties, and thermal physical properties of this alloy. Focusing on its application scenarios in Accident Tolerant Fuel (ATF) for Light Water Reactors (LWRs), the advantages and disadvantages of different preparation processes, performance influencing factors, and radiation behavior characteristics were systematically analyzed and compared with those of mainstream nuclear fuel materials. The research showed that the U-50Zr alloy had excellent thermal conductivity and a low irradiation swelling rate, and could maintain good mechanical properties at high temperatures, demonstrating great potential in applications such as light water reactor (LWR) fuel. At the same time, the stability of the alloy's microstructure and phase transformation behavior had a significant impact on its performance. Through heat treatment and irradiation treatment, its performance was further optimized. Additionally, the bonding effect and influencing factors between the alloy and the cladding material, as well as the irradiation stability and safety in actual reactors were discussed. Based on the existing research, it is believed that the U-50Zr alloy has broad application prospects in the nuclear fuel field, but further research is needed to overcome existing challenges and achieve widespread application.

导出引用

王兴栋, 易致豪, 田浩, 邓麒林, 史晓龙, 胡红军. U-50Zr合金在核燃料领域的性能与应用潜力研究[J]. 精密成形工程. 2026, 18(6): 260-274 https://doi.org/10.3969/j.issn.1674-6457.2026.06.022

WANG Xingdong, YI Zhihao, TIAN Hao, DENG Qilin, SHI Xiaolong, HU Hongjun. Performance and Application Potential of U-50Zr Alloy in Nuclear Fuel[J]. Journal of Netshape Forming Engineering. 2026, 18(6): 260-274 https://doi.org/10.3969/j.issn.1674-6457.2026.06.022

中图分类号： TG146.4

参考文献

[1] 邵宽. 核燃料中裂变产物行为的理论研究[D]. 上海: 中国科学院大学(中国科学院上海应用物理研究所), 2017.
SHAO K.Theoretical Studies of Fission Product Behavior in Nuclear Fuel[D]. Shanghai: Shanghai Institute of Applied Physics, Chinese Academy of Sciences, 2017.
[2] TERRANI K A, JOLLY B C, TRAMMELL M P, et al.Architecture and Properties of TCR Fuel Form[J]. Journal of Nuclear Materials, 2021, 547: 152781.
[3] ZHOU X W, ZHANG J, HOU M D, et al.Hot-Pressing of BeO Ceramics and Its Thermal Conductivity and Flexural Strength[J]. Ceramics International, 2024, 50(18): 33717-33724.
[4] XIAO H X, WANG X M, LONG C S, et al.Investigation of the Mechanical Properties of ZrO₂-Doped UO₂ Ceramic Pellets by Indentation Technique[J]. Journal of Nuclear Materials, 2018, 509: 482-487.
[5] MAIORINO J R, STEFANI G L, MOREIRA J M L, et al. Feasibility to Convert an Advanced PWR from UO₂ to a Mixed U/ThO₂ Core-Part I: Parametric Studies[J]. Annals of Nuclear Energy, 2017, 102: 47-55.
[6] CHEN J H, ZHU L L, LIAO Y H, et al.Hydrothermal Corrosion Behavior of CrN/Cr₂N-ZrN Ceramic as a Surrogate Nuclear Fuel[J]. International Journal of Applied Ceramic Technology, 2025, 22(1): e14914.
[7] 王挺, 恽迪, 杜沛南, 等. 快堆金属燃料的研究进展[J]. 材料导报, 2026, 40(10): 183-197.
WANG T, YUN D, DU P N, et al.Research Progress on Metallic Fuels for Fast Reactors[J]. Materials Review, 2026, 40(10): 183-197.
[8] BASAK C B.Phase Transformations in U-Zr Alloy System[J]. BARC Newsletter, 2010, 316: 1-8.
[9] HOU Y D, DONG Y L, GAO C T, et al.U-50Zr Helical Cruciform Fuel Performance Analysis Based on MOOSE Framework[J]. Annals of Nuclear Energy, 2024, 204: 110529.
[10] 李冠兴, 周邦新, 肖岷, 等. 中国新一代核能核燃料总体发展战略研究[J]. 中国工程科学, 2019, 21(1): 6-11.
LI G X, ZHOU B X, XIAO M, et al.Research on Overall Development Strategy of New-Generation Nuclear Fuels in China[J]. Strategic Study of CAE, 2019, 21(1): 6-11.
[11] MA J J, HAN X F, CAI X X, et al.High-Temperature Mechanical and Dynamical Properties of γ-(U,Zr) Alloys[J]. Materials, 2023, 16(7): 2623.
[12] 丁雪健, 黄灏, 霍永忠. 核燃料裂变气体辐照肿胀的相场模拟与分析[J]. 力学季刊, 2015, 36(4): 566-573.
DING X J, HUANG H, HUO Y Z.Phase Field Simulation and Analysis of Nuclear Fission Gas Irradiation Swelling[J]. Chinese Quarterly of Mechanics, 2015, 36(4): 566-573.
[13] MCDEAVITT S M, SHAO L, TSVETKOV P V, et al.Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels[R]. College Station: Texas A&M University, 2014.
[14] LI Y, HONG G, LI M Y, et al.Thermal Deformation Behavior and Constitutive Equation of Uranium-50wt.% Zirconium Nuclear Fuel[J]. Journal of Nuclear Materials and Engineering, 2024, 12: 100389.
[15] 王华才, 杨大伟, 程焕林, 等. 压水堆燃料棒UO₂燃料芯块与锆合金包壳化学相互作用层研究[J]. 核技术, 2023, 46(9): 103-110.
WANG H C, YANG D W, CHENG H L, et al.Chemical Interaction Layer between Uranium Oxide Fuel Pellet and Zirconium Alloy Cladding in Pressurized Water Reactor[J]. Nuclear Techniques, 2023, 46(9): 103-110.
[16] HUBER Z F, CONTE E R, LAVENDER C A, et al.Casting and Characterization of U-50Zr[R]. Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Lightbridge Corporation, Reston, VA(United States), 2023.
[17] AHN S, IRUKUVARGHULA S, MCDEAVITT S M.Thermophysical Investigations of the Uranium-Zirconium Alloy System[J]. Journal of Alloys and Compounds, 2014, 611: 355-362.
[18] XIE Y, VOGEL S C, BENSON M T, et al.Phase Evolution of U-Zr System in a Thermal Cycling Neutron Diffraction Experiment: As-Cast U-35Zr and U-50Zr[J]. Journal of Nuclear Materials, 2022, 564: 153681.
[19] BAGCHI A C, PRASAD G J, KHAN K B, et al.A Study on Zirconium Rich Uranium-Zirconium Alloys[J]. Transactions of the Indian Institute of Metals, 2014, 67(1): 123-130.
[20] BASAK C B, POSWAL A K.Structure and Stability of δ-UZr2 Phase in U-50wt% Zr Alloy[J]. Philosophical Magazine, 2022, 102(9): 787-802.
[21] EICHEL D.Atomic Diffusion in the U-50Zr Nuclear Fuel System[D]. College Station: Texas A&M University,2013.
[22] 李岩峰, 郭洪, 李明阳, 等. 核燃料U-50%Zr合金的组织及热变形行为[J]. 金属热处理, 2025, 50(2): 29-36.
LI Y F, GUO H, LI M Y, et al.Microstructure and Hot Deformation Behavior of U-50%Zr Alloy for Nuclear Fuel[J]. Heat Treatment of Metals, 2025, 50(2): 29-36.
[23] SEN A, BACHHAV M, PU X F, et al.Irradiation Effects on Stability of δ-UZr₂ Phase in U-50wt% Zr Alloy[J]. Journal of Nuclear Materials, 2023, 576: 154251.
[24] LA Y X, WEN C Y, FENG L N, et al.Phase-Field Simulation of Spinodal Decomposition in U-50Zr Metallic Nuclear Fuel[J]. Nanomaterials, 2024, 14(19): 1548.
[25] BASAK C B, PRABHU N, KRISHNAN M.On the Formation Mechanism of UZr₂ Phase[J]. Intermetallics, 2010, 18(9): 1707-1712.
[26] BEAUSOLEIL G L, CINBIZ M N, YAO T, et al.U-50Zr Microstructure and Property Assessment for LWR Applications[R]. Idaho Falls:Idaho National Laboratory (INL) , 2021.
[27] 蔡孟珂, 丛腾龙, 顾汉洋. U-50Zr螺旋十字燃料热力耦合特性分析[J]. 哈尔滨工程大学学报, 2022, 43(12): 1772-1777.
CAI M K, CONG T L, GU H Y.Thermal-Mechanical Coupled Performance Analysis of U-50Zr Helical Cruciform Fuel[J]. Journal of Harbin Engineering University, 2022, 43(12): 1772-1777.
[28] HUA Z L, YAO T K, KHANOLKAR A, et al.Intragranular Thermal Transport in U-50Zr[J]. Journal of Nuclear Materials, 2020, 534: 152145.
[29] YAO T K, WAGNER A, LIU X, et al.On Spinodal-Like Phase Decomposition in U-50 Zr Alloy[J]. Materialia, 2020, 9: 100592.
[30] MCCOY K M, HUBER Z F, ATHON M T, et al.Thermomechanical Processing of Uranium Alloys with 10 and 50 Weight Percent Zirconium[R]. Richland: Pacific Northwest National Laboratory (PNNL), 2020.
[31] 包春玲, 金德华, 张有为, 等. 锆及锆合金铸造工艺与成型技术研究进展[J]. 材料导报, 2024, 38(S2): 367-371.
BAO C L, JIN D H, ZHANG Y W, et al.Research Progress of Casting Technology and Forming Technology of Zirconium and Zirconium Alloys[J]. Materials Reports, 2024, 38(S2): 367-371.
[32] 袁显宝, 石强, 张彬航, 等.包壳相关行为对严重事故进程的影响分析[J].科学技术与工程, 2022, 22(19): 8333-8339.
YUAN X B, SHI Q, ZHANG B H, et al.Analysis of Cladding Related Behavior on Severe Accident Process[J]. Science Technology and Engineering, 2022, 22(19): 8333-8339.
[33] 王瑶, 李金山, 陈波, 等. Cr涂层锆合金耐事故燃料包壳材料高温蒸汽氧化行为研究进展[J]. 稀有金属材料与工程, 2024, 53(11): 3271-3280.
WANG Y, LI J S, CHEN B, et al.Research Progress on High-Temperature Steam Oxidation Behavior of Cr-Coated Zirconium Alloy as Accident-Tolerant Fuel Cladding[J]. Rare Metal Materials and Engineering, 2024, 53(11): 3271-3280.
[34] RIBIS J, ONIMUS F, BÉCHADE J L, et al. Experimental Study and Numerical Modelling of the Irradiation Damage Recovery in Zirconium Alloys[J]. Journal of Nuclear Materials, 2010, 403(1/2/3): 135-146.
[35] 张海芹, 王旭峰, 渠静雯, 等. Zr-4合金包壳管维氏硬度与强度关系研究[J]. 钛工业进展, 2023, 40(6): 36-40.
ZHANG H Q, WANG X F, QU J W, et al.Study on Correlation of Vickers Hardness and Strength of Zr-4 Alloy Cladding Tube[J]. Titanium Industry Progress, 2023, 40(6): 36-40.
[36] ADITYA RAMA KAMALANATH P, SARKAR A. Tensile Behavior of Cryorolled Zircaloy-2[J]. American Journal of Materials Science, 2012, 2(5): 138-141.
[37] MOTTA A T, COUET A, COMSTOCK R J.Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding[J]. Annual Review of Materials Research, 2015, 45: 311-343.
[38] 章勋亮, 张聪惠, 朱文光, 等. 热处理工艺参数对双相Zr-2.5Nb合金组织演变机制及力学性能的影响[J]. 稀有金属材料与工程, 2024, 53(9): 2571-2579.
ZHANG X L, ZHANG C H, ZHU W G, et al.Effect of Heat Treatment Conditions on Microstructure Evolution and Mechanical Properties of Zr-2.5Nb Alloy[J]. Rare Metal Materials and Engineering, 2024, 53(9): 2571-2579.
[39] LEE S U, KIM H, ŠEVEČEK M, et al. High-Temperature Creep Behavior of Cr-Coated Optimized ZIRLO™ Cladding via Inverse Analysis Based on Finite Element Method[J]. Nuclear Engineering and Design, 2025, 444: 114383.
[40] 刘家正. 高燃耗下M5合金包壳燃料棒稳态和瞬态性能分析[J]. 核技术, 2010, 33(2): 112-116.
LIU J Z.Steady and Transient Performance Analysis of M5 Fuel Rods at High Burnup[J]. Nuclear Techniques, 2010, 33(2): 112-116.
[41] 李兵. 金属材料在核能中的应用[J]. 金属世界, 2004(5): 40.
LI B.Application of Metallic Materials in Nuclear Energy[J]. Metal World, 2004 (5): 40.
[42] BRITT T C.Innovative Fuel Design to Improve Proliferation Management[D]. Richmond: Virginia Commonwealth University, 2018.
[43] 刘海涛, 孙宇, 刘振宇, 等. 热轧工艺对超纯Cr17铁素体不锈钢成形性能的影响[J]. 材料热处理学报, 2011, 32(5): 46-50.
LIU H T, SUN Y, LIU Z Y, et al.Effect of Hot Rolling Process on Formability of Ultra-Purified Cr17 Ferritic Stainless Steel[J]. Transactions of Materials and Heat Treatment, 2011, 32(5): 46-50.
[44] 喻海良. 深冷轧制制备高性能金属材料研究进展[J]. 中国机械工程, 2020, 31(1): 89-99.
YU H L.Progresses in Fabrication of High-Performance Metals by Using Cryorolling[J]. China Mechanical Engineering, 2020, 31(1): 89-99.
[45] BEAN C H, MACHEREY R E, LINDGREN J R.Roll Cladding Uranium-Zirconium and Uranium-Zirconium- Niobium Alloys with Zircaloy-2 for Plate-Type Fuel Elements[R]. Argonne:Argonne National Laboratory, 1958.
[46] 刘禹江, 杜文玉, 王延, 等. 铜包铝层状材料的制备技术、应用现状及发展趋势研究[J]. 精密成形工程, 2025, 17(7): 119-137.
LIU Y J, DU W Y, WANG Y, et al.Preparation Technology, Application Status, and Development Trends of Copper-Clad Aluminum Laminated Materials[J]. Journal of Netshape Forming Engineering, 2025, 17(7): 119-137.
[47] 杨晖, 潘少明. 基体表面粗糙度对涂层结合强度的影响[J]. 热加工工艺, 2008, 37(15): 118-121.
YANG H, PAN S M.Effect of Substrate Surface Roughness on Bond Strength of Coatings[J]. Hot Working Technology, 2008, 37(15): 118-121.
[48] 杨春洋, 孙有平, 何江美, 等. 轧制温度对大应变轧制Al-4.5Cu-1.5Mg-0.1Sc合金组织与性能的影响[J]. 矿冶工程, 2022, 42(2): 132-135.
YANG C Y, SUN Y P, HE J M, et al.Effect of Temperature on Microstructure and Properties of Large-Strain Rolled Al-4.5Cu-1.5Mg-0.1Sc Alloy[J]. Mining and Metallurgical Engineering, 2022, 42(2): 132-135.
[49] 刘民章. 4343A/3003/4343A铝合金三层复合材料加工工艺研究[J]. 铝加工, 2015(3): 46-49.
LIU M Z. Research on Fabrication Process for 4343A/3003/4343A Aluminium Alloy Composite[J]. Aluminium Fabrication, 2015(3): 46-49.
[50] 张忠华, 陈慧琴, 朱雪彤. 轧制工艺参数对C70250铜合金薄板冷轧残余应力的影响[J]. 铜业工程, 2025(5): 10-18.
ZHANG Z H, CHEN H Q, ZHU X T.Parameters on Residual Stress of C70250 Copper Alloy Sheet in Cold Rolling with Different Rolling Process Parameters[J]. Copper Engineering, 2025(5): 10-18.
[51] 刘学强, 左家栋, 王亚强, 等. 锆合金包壳表面纳米多层涂层的研究进展[J]. 中国材料进展,2024,43(12): 1125-1137.
LIU X Q, ZUO J D, WANG Y Q, et al.Research Progress of Nanolaminated Coatings on Zirconium Alloy Cladding[J]. Materials China, 2024, 43(12): 1125-1137.