偏滤器用钨基材料的热负荷损伤行为研究进展

doi:10.11900/0412.1961.2024.00309

金属学报

2025, Vol. 61

Issue (7): 961-978 DOI: 10.11900/0412.1961.2024.00309

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偏滤器用钨基材料的热负荷损伤行为研究进展

罗来马¹^,²^,³, 陈宇¹, 姚刚⁴, 朱晓勇¹^,²^,³(

), 朱大焕⁵, 吴玉程¹^,²^,³

1 合肥工业大学材料科学与工程学院合肥 230009
2 合肥工业大学高性能铜合金材料及成形加工教育部工程研究中心合肥 230009
3 合肥工业大学有色金属与加工技术国家地方联合工程研究中心合肥 230009
4 内蒙古科技大学材料科学与工程学院包头 014010
5 中国科学院合肥物质科学研究院等离子体物理研究所合肥 230031

Research Progress on Heat Load Damage Behavior of Tungsten-Based Materials for Divertor

LUO Laima¹^,²^,³, CHEN Yu¹, YAO Gang⁴, ZHU Xiaoyong¹^,²^,³(

), ZHU Dahuan⁵, WU Yucheng¹^,²^,³

1 School of Materials Science and Engineering, Hefei University of Technology, Hefei 230009, China
2 Engineering Research Center of High-Performance Copper Alloy Materials and Processing, Ministry of Education, Hefei University of Technology, Hefei 230009, China
3 National-Local Joint Engineering Research Centre of Nonferrous Metals and Processing Technology, Hefei University of Technology, Hefei 230009, China
4 School of Materials Science and Engineering, Inner Mongolia University of Science and Technology, Baotou 014010, China
5 Institute of Plasma Physics, Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, China

引用本文:

罗来马, 陈宇, 姚刚, 朱晓勇, 朱大焕, 吴玉程. 偏滤器用钨基材料的热负荷损伤行为研究进展[J]. 金属学报, 2025, 61(7): 961-978.
Laima LUO, Yu CHEN, Gang YAO, Xiaoyong ZHU, Dahuan ZHU, Yucheng WU. Research Progress on Heat Load Damage Behavior of Tungsten-Based Materials for Divertor[J]. Acta Metall Sin, 2025, 61(7): 961-978.

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摘要:

有限的能源无法满足人类社会长期发展的需求，核聚变能源被视为保护环境和满足未来能源需求的重要解决方案之一。然而，为确保聚变堆的正常运行，解决托卡马克(Tokamak)装置中面向等离子体的偏滤器热负荷损伤问题至关重要。W因具有高熔点、低物理溅射率、低氘滞留以及优异的力学性能等优点而成为核聚变堆中偏滤器部位首选的面向等离子体材料(PFMs)。在聚变堆运行期间，钨基PFMs会受到持续的热负荷损伤，通常偏滤器部位需承受5~20 MW/m²高热峰值的稳态热负荷和功率密度高达约2 GW/m²的瞬态热负荷。因此，W在热负荷作用下的损伤行为及抑制损伤策略已成为当前研究的热点问题。本文根据国内外现有研究成果，阐述了纯W、合金化钨、弥散强化钨在热负荷作用下的损伤行为。针对钨基材料的热负荷损伤演变情况及抑制损伤策略进行总结与展望，进而为后续研究工作提供参考。

关键词 ：偏滤器, 钨基材料, 热负荷, 损伤行为, 抑制损伤策略

Abstract：

Limited energy resources cannot meet the long-term developmental needs of human society. As such, nuclear fusion energy is considered a key solution for environmental protection and meeting future energy demands. However, to ensure the reliable operation of fusion reactors, addressing heat load damage to the divertor facing plasma in tokamak devices is crucial. The divertor, an indispensable core component of fusion devices, plays essential roles in these devices, including the removal of heat load generated via scraping layers and radiation and protection of the main vacuum chamber, auxiliary heating systems, and diagnostic systems, thereby ensuring the safe and stable operation of nuclear fusion reactors. Nevertheless, due to harsh operational conditions, the divertor is prone to damage, limiting the stable operation of long-pulse, high-parameter plasmas. W is critical in the divertor of fusion reactors, primarily owing to its high melting point, low physical sputtering rate, low deuterium retention, and excellent mechanical properties, allowing it to perform stably under extreme conditions. However, tungsten materials have several limitations, including a high ductile-brittle transition temperature, a low recrystallization temperature, and susceptibility to activation. Therefore, it is necessary to regulate, modify, and optimize these materials to enhance the performance of plasma-facing materials (PFMs). Such improvements aim to increase their resilience under extreme environments, minimize damage risks under high heat loads, and enhance heat load resistance, thereby ensuring the long-term stable operation of the divertor in fusion reactors and to meet future energy challenges. The working conditions of fusion reactors are extremely harsh, with the divertor region experiencing continuous heat load damage. It typically faces steady-state heat loads with peak values as high as 5-20 MW/m² and transient heat loads of up to ~2 GW/m². These heat loads can cause melting and cracking on both sides of the divertor cassette, posing a risk of reactor failure. Consequently, the study of the heat load damage behavior in tungsten-based PFMs as well as development of damage mitigation strategies have become hot topics in fusion research. This paper reviews current research efforts, both domestic and international, related to the damage behavior of pure tungsten, tungsten alloys, and dispersed phase-strengthened tungsten under heat load conditions. Additionally, it summarizes and forecasts the evolution of heat load damage in tungsten-based materials and presents strategies for damage mitigation, thereby providing a reference for future research endeavors.

Key words： divertor tungsten-based material heat load damage behavior strategies to inhibit the damage

收稿日期: 2024-09-03

ZTFLH:

TG146.1

基金资助:国家重点研发计划项目(2019YFE03120002);国家重点研发计划项目(2022YFE03140001);国家重点研发计划项目(2022YFE03030003);中央高校基本科研业务费专项资金项目(JZ2023HGQB0164);国家资助博士后研究人员计划项目(GZC20230656);安徽省自然科学基金项目(2108085J21);安徽省自然科学基金项目(2308085QE154);安徽省重点研发计划项目(202104A05020045)

通讯作者: 朱晓勇，zhuxiaoyong@hfut.edu.cn，主要从事钨基复合材料制备、加工及热负荷研究

作者简介: 罗来马，男，1980年生，教授，博士

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图1 磁约束核聚变托卡马克(Tokamak)偏滤器结构设计示意图[2,3]及其热负荷加载场景[13,26]

图2 加载3 GW/m2热负荷后W样品表面的SEM像[27]

图3 主裂纹和二次裂纹典型分布以及不同加载条件下纯W表面开裂情况的SEM像[34]

图4 小型纯W偏滤器模型(SSMU)在高热流测试后的表面形貌[37]

图5 高功率热负荷测试前后再结晶W和电子束选区熔化(SEBM) W的SEM像[39]

表1 超细晶W的抗热负荷能力统计[51,52]

图6 经过氘(D)等离子体暴露热负荷实验后的W和W-3%Ta合金的SEM像[58]

图7 不同高功率密度加载下W-V合金的SEM像[61]

图8 纯W和W-K合金热负荷实验后的SEM像[68]

表2 单次热负荷测试中W-K-xY合金和纯W的耐热负荷能力对比[71~73]

图9 热负荷加载后各试样表面的FESEM像[87]

图10 不同功率密度下W-2.0%Y2O3复合材料经100次脉冲热负荷实验后的横向-法向(TD-ND)和轧向-横向(RD-TD)表面形貌[88]

图11 热负荷实验后试样表面和截面的SEM像[92,102]

表3 经瞬态热负荷后纯W及钨基复合材料损伤行为对比[83,85,88,90,92,97,102,103,106~112]

1	International Energy Agency. World energy outlook 2024 [R]. Paris: International Energy Agency, 2024
2	Kleyn A W, Lopes Cardozo N J, Samm U. Plasma-surface interaction in the context of ITER [J]. Phys. Chem. Chem. Phys., 2006, 8: 1761 pmid: 16633660
3	Hirai T, Escourbiac F, Carpentier-Chouchana S, et al. ITER tungsten divertor design development and qualification program [J]. Fusion Eng. Des., 2013, 88: 1798
4	Barabash V, Akiba M, Mazul I, et al. Selection, development and characterisation of plasma facing materials for ITER [J]. J. Nucl. Mater., 1996, 233-237: 718
5	Guseva M I, Suvorov A L, Korshunov S N, et al. Sputtering of beryllium, tungsten, tungsten oxide and mixed W-C layers by deuterium ions in the near-threshold energy range [J]. J. Nucl. Mater., 1999, 266-269: 222
6	Reiser J, Rieth M, Dafferner B, et al. Tungsten foil laminate for structural divertor applications-basics and outlook [J]. J. Nucl. Mater., 2012, 423: 1
7	Rubel M. Structure materials in fusion reactors: Issues related to tritium, radioactivity and radiation-induced effects [J]. Fusion Sci. Technol., 2010, 57: 474
8	Dicarlo J A, Stanley J T. Energy dependence of electron-induced radiation damage in tungsten [J]. Radiat. Eff., 1971, 10: 259
9	Pitts R A, Bonnin X, Escourbiac F, et al. Physics basis for the first ITER tungsten divertor [J]. Nucl. Mater. Energy, 2019, 20: 100696
10	Wan Y X, Li J G, Liu Y, et al. Overview of the present progress and activities on the CFETR [J]. Nucl. Fusion, 2017, 57: 102009
11	Barrett T R, Ellwood G, Pérez G, et al. Progress in the engineering design and assessment of the European DEMO first wall and divertor plasma facing components [J]. Fusion Eng. Des., 2016: 109-111: 917
12	Coenen J W, Antusch S, Aumann M, et al. Materials for DEMO and reactor applications—Boundary conditions and new concepts [J]. Phys. Scr., 2016, T167: 014002
13	Linke J, Du J, Loewenhoff T, et al. Challenges for plasma-facing components in nuclear fusion [J]. Matter Radiat. Extremes, 2019, 4: 056201
14	Li Y, Morgan T W, Vermeij T, et al. Recrystallization-mediated crack initiation in tungsten under simultaneous high-flux hydrogen plasma loads and high-cycle transient heating [J]. Nucl. Fusion, 2021, 61: 046018
15	Durif A, Richou M, Kermouche G, et al. Numerical study of the influence of tungsten recrystallization on the divertor component lifetime [J]. Int. J. Fract., 2021, 230: 83
16	Li C J, Zhu D H, Ding R, et al. Numerical analysis of recrystallization behaviors for W monoblock under cyclic high heat flux [J]. Nucl. Mater. Energy, 2022, 32: 101227
17	Hirai T, Ezato K, Majerus P. ITER relevant high heat flux testing on plasma facing surfaces [J]. Mater. Trans., 2005, 46: 412
18	Konings R J M. Comprehensive Nuclear Materials [M]. Amsterdam: Elsevier, 2012: 551
19	Raffray A R, Nygren R, Whyte D G, et al. High heat flux components-readiness to proceed from near term fusion systems to power plants [J]. Fusion Eng. Des., 2010, 85: 93
20	Mazul I, Alekseev A, Belyakov V, et al. Russian development of enhanced heat flux technologies for ITER first wall [J]. Fusion Eng. Des., 2012, 87: 437
21	Li C J. Study on the surface damages of tungsten under high plasma heat fluxes in Tokamak [D]. Hefei: University of Science and Technology of China, 2020
21	李长君. 托卡马克等离子体高热流下钨表面损伤行为研究 [D]. 合肥: 中国科学技术大学, 2020
22	Gao B F. Material damage of divertor and limiter and its impact on plasma operation in EAST [D]. Hefei: University of Science and Technology of China, 2023
22	高彬富. EAST偏滤器和限制器材料损伤及其对等离子体运行影响的研究 [D]. 合肥: 中国科学技术大学, 2023
23	Gao B F, Ding R, Xie H, et al. Plasma-facing components damage and its effects on plasma performance in EAST tokamak [J]. Fusion Eng. Des., 2020, 156: 111616
24	Wu Y C, Yao G, Luo L M, et al. Research progress in heat load damage behavior of tungsten and tungsten base materials for nuclear fusion reactor [J]. Chin. J. Nonferrous Met., 2018, 28: 719
24	吴玉程, 姚刚, 罗来马等. 核聚变堆用钨及钨基材料热负荷损伤行为的研究进展 [J]. 中国有色金属学报, 2018, 28: 719
25	Mcdowell D L. Basic issues in the mechanics of high cycle metal fatigue [J]. Int. J. Fract., 1996, 80: 103
26	Xie Z M, Miao S, Liu R, et al. Recrystallization and thermal shock fatigue resistance of nanoscale ZrC dispersion strengthened W alloys as plasma-facing components in fusion devices [J]. J. Nucl. Mater., 2017, 496: 41
27	Minissale M, Durif A, Kermouche G, et al. Grain growth and damages induced by transient heat loads on W [J]. Phys. Scr., 2021, 96: 124032
28	Seo M, Echols J R, Winfrey A L. Morphological and nanomechanical changes in tungsten in high heat flux conditions [J]. npj Mater. Degrad., 2020, 4: 30
29	Seo M, Wang K, Echols J R, et al. Microstructure deformation and near-pore environment of resolidified tungsten in high heat flux conditions [J]. J. Nucl. Mater., 2022, 565: 153725
30	Gebhart T E, Baylor L R, Rapp J, et al. Characterization of an electrothermal plasma source for fusion transient simulations [J]. J. Appl. Phys., 2018, 123: 033301
31	Gebhart T E, Martine-Rodriguez R A, Baylor L R, et al. Material impacts and heat flux characterization of an electrothermal plasma source with an applied magnetic field [J]. J. Appl. Phys., 2017, 122: 063302
32	Yang W H, Jiang S, Chen L, et al. Transient heat thermal load characteristics produced by a three-electrode capillary discharge generator [J]. Phys. Plasmas, 2021, 28: 113503
33	Chen L, Yang W H, Fan H, et al. The injected plasma triggered breakdown of the trigatron spark gap [J]. Phys. Plasmas, 2020, 27: 023501
34	Jiang S, Chen L, Li W H, et al. Evolution of tungsten degradation under different cyclic ELM-like high heat flux plasma [J]. J. Nucl. Mater., 2024, 588: 154762
35	Li W H, He Y Z, Jiang S, et al. Research on corrosion and damage characteristics of tungsten caused by capillary discharge transient high thermal load [J]. Proc. CSEE, 2023, 43: 6914
35	李伟昊, 贺玉哲, 蒋仕等. 毛细管放电瞬态高热负荷对钨靶侵蚀损伤特性研究 [J]. 中国电机工程学报, 2023, 43: 6914
36	Lian Y Y, Liu X, Feng F, et al. Manufacturing and high heat flux testing of brazed flat-type W/CuCrZr plasma facing components [J]. Plasma Sci. Technol., 2016, 18: 184
37	Fukuda M, Seki Y, Ezato K, et al. Effect of cyclic heat loading on pure tungsten for the ITER divertor [J]. J. Nucl. Mater., 2020, 542: 152509
38	Pintsuk G, Missirlian M, Luo G N, et al. High heat flux testing of newly developed tungsten components for WEST [J]. Fusion Eng. Des., 2021, 173: 112835
39	Dorow-Gerspach D, Kirchner A, Loewenhoff T, et al. Additive manufacturing of high density pure tungsten by electron beam melting [J]. Nucl. Mater. Energy, 2021, 28: 101046
40	Majerus P, Duwe R, Hirai T, et al. The new electron beam test facility JUDITH II for high heat flux experiments on plasma facing components [J]. Fusion Eng. Des., 2005, 75-79: 365
41	Yang G Y, Yang P W, Yang K, et al. Effect of processing parameters on the density, microstructure and strength of pure tungsten fabricated by selective electron beam melting [J]. Int. J. Refract. Met. Hard Mater., 2019, 84: 105040
42	Zhou X, Liu X H, Zhang D D, et al. Balling phenomena in selective laser melted tungsten [J]. J. Mater. Process. Technol., 2015, 222: 33
43	Zhou X, Liu W. Melting and solidifying behavior in single layer selective laser of pure tungsten powder [J]. Chin. J. Lasers, 2016, 43: 0503006
43	周鑫, 刘伟. 纯钨单层铺粉激光选区熔化/凝固行为 [J]. 中国激光, 2016, 43: 0503006
44	Bose A, Schuh C A, Tobia J C, et al. Traditional and additive manufacturing of a new Tungsten heavy alloy alternative [J]. Int. J. Refract. Met. Hard Mater., 2018, 73: 22
45	Zi X H, Chen C, Wang X J, et al. Spheroidisation of tungsten powder by radio frequency plasma for selective laser melting [J]. Mater. Sci. Technol., 2018, 34: 735
46	Mostafaei A, Elliott A M, Barnes J E, et al. Binder jet 3D printing—Process parameters, materials, properties, modeling, and challenges [J]. Prog. Mater. Sci., 2021, 119: 100707
47	Wu Y C. The routes and mechanism of plasma facing tungsten materials to improve ductility [J]. Acta Metall. Sin., 2019, 55: 171 doi: 10.11900/0412.1961.2018.00404
47	吴玉程. 面向等离子体W材料改善韧性的方法与机制 [J]. 金属学报, 2019, 55: 171 doi: 10.11900/0412.1961.2018.00404
48	Li P, Lin Q, Zhou Y F, et al. TEM analysis of microstructure evolution process of pure tungsten under high pressure torsion [J]. Acta Metall. Sin., 2019, 55: 521 doi: 10.11900/0412.1961.2018.00165
48	李萍, 林泉, 周玉峰等. 纯W高压扭转显微组织演化过程TEM分析 [J]. 金属学报, 2019, 55: 521
49	Ganeev A V, Islamgaliev R K, Valiev R Z. Refinement of tungsten microstructure upon severe plastic deformation [J]. Phys. Met. Metall., 2014, 115: 139
50	Kecskes L J, Cho K C, Dowding R J, et al. Grain size engineering of bcc refractory metals: Top-down and bottom-up-application to tungsten [J]. Mater. Sci. Eng., 2007, A467: 33
51	Zhou Z J, Pintsuk G, Linke J, et al. Transient high heat load tests on pure ultra-fine grained tungsten fabricated by resistance sintering under ultra-high pressure [J]. Fusion Eng. Des., 2010, 85: 115
52	Zhang X X, Yan Q Z, Lang S T, et al. Thermal shock performance of sintered pure tungsten with various grain sizes under transient high heat flux test [J]. J. Fusion Energy, 2016, 35: 666
53	Zhang X, Tian J, Xue M T, et al. Ta-W refractory alloys with high strength at 2000 ^oC [J]. Acta Metall. Sin., 2022, 58: 1253
53	张旭, 田谨, 薛敏涛等. 2000 ℃高温高承载的Ta-W难熔合金 [J]. 金属学报, 2022, 58: 1253
54	Wang Z, Yuan Y, Arshad K, et al. Effects of tantalum concentration on the microstructures and mechanical properties of tungsten-tantalum alloys [J]. Fusion Eng. Des., 2017, 125: 496
55	Linke J, Loewenhoff T, Massaut V, et al. Performance of different tungsten grades under transient thermal loads [J]. Nucl. Fusion, 2011, 51: 073017
56	Li B S, Marrow T J, Armstrong D E J. Measuring the brittle-to-ductile transition temperature of tungsten-tantalum alloy using chevron-notched micro-cantilevers [J]. Scr. Mater., 2020, 180: 77
57	Gonderman S, Tripathi J K, Sinclair G, et al. Effects of in situ dual ion beam (He⁺ and D⁺) irradiation with simultaneous pulsed heat loading on surface morphology evolution of tungsten-tantalum alloys [J]. Nucl. Fusion, 2018, 58: 026016
58	Nogami S, Wirtz M, Lied P, et al. Thermal shock behavior under deuterium plasma exposure of tungsten-tantalum alloys [J]. Phys. Scr., 2021, 96: 114011
59	Arshad K, Guo W, Wang J, et al. Influence of vanadium precursor powder size on microstructures and properties of W-V alloy [J]. Int. J. Refract. Met. Hard Mater., 2015, 50: 59
60	Arshad K, Zhao M Y, Yuan Y, et al. Effects of vanadium concentration on the densification, microstructures and mechanical properties of tungsten vanadium alloys [J]. J. Nucl. Mater., 2014, 455: 96
61	Arshad K, Ding D, Wang J, et al. Surface cracking of tungsten-vanadium alloys under transient heat loads [J]. Nucl. Mater. Energy, 2015, 3-4: 32
62	Cui H J, Liu N, Luo L M, et al. A prospect of using ternary W-5 wt%V-5 wt%Ta alloy manufactured by mechanical alloying and spark plasma sintering as plasma-facing material [J]. J. Alloys Compd., 2022, 903: 163899
63	Zhao B L, Xie Z M, Liu R, et al. Fabrication of an ultrafine-grained W-ZrC-Re alloy with high thermal stability [J]. Fusion Eng. Des., 2021, 164: 112208
64	Du F Y, Xu Y P, Tian Y, et al. Comparative study of microstructural evolution in W-3Re alloy under high-temperature conditions: High heat flux loading versus furnace heating [J]. Nucl. Mater. Energy, 2024, 39: 101646
65	Watanabe S, Nogami S, Reiser J, et al. Tensile and impact properties of tungsten-rhenium alloy for plasma-facing components in fusion reactor [J]. Fusion Eng. Des., 2019, 148: 111323
66	Fukuda M, Nogami S, Hasegawa A, et al. Tensile properties of K-doped W-3%Re [J]. Fusion Eng. Des., 2014, 89: 1033
67	Ma X L, Wang T, Zhang X X, et al. Surface modification and deuterium retention in hot-rolled potassium doped tungsten alloy exposed to deuterium plasma [J]. J. Nucl. Mater., 2022, 568: 153890
68	Ma X L, Feng F, Zhang X X, et al. Effect of Fe¹¹⁺ ion combined with helium and deuterium plasmas irradiation on the transient thermal shock behaviors of pure and potassium-doped tungsten [J]. J. Nucl. Mater., 2023, 573: 154100
69	Wang Y J, Yan Q Z. Preparation of hot-rolled potassium doped tungsten (KW) thick plate and performance of KW-Cu monoblock mock-ups under high heat flux testing [J]. Nucl. Mater. Energy, 2020, 23: 100744
70	Fu X G, Zheng M X, Liu X, et al. Vacancy-type defects in H + 6%He neutral beam irradiated WK alloy probed by slow positron beam [J]. Phys. Status Solidi, 2022, 219A: 2100497
71	Chen L Q, Li S, Qiu W B, et al. Combining the K-bubble strengthening and Y-doping: Microstructure, mechanical/thermal properties, and thermal shock behavior of W-K-Y alloys [J]. Int. J. Refract. Met. Hard Mater., 2022, 103: 105739
72	Hirai T, Pintsuk G, Linke J, et al. Cracking failure study of ITER-reference tungsten grade under single pulse thermal shock loads at elevated temperatures [J]. J. Nucl. Mater., 2009, 390-391: 751
73	Uytdenhouwen I, Decréton M, Hirai T, et al. Influence of recrystallization on thermal shock resistance of various tungsten grades [J]. J. Nucl. Mater., 2007, 363-365: 1099
74	He B, Huang B, Xiao Y, et al. Preparation and thermal shock characterization of yttrium doped tungsten-potassium alloy [J]. J. Alloys Compd., 2016, 686: 298
75	Shi J B, Song J P, Liang M X, et al. Effects of minor rhenium additions on the thermal properties and recrystallization temperature of tungsten alloy [J]. Nucl. Mater. Energy, 2024, 38: 101609
76	Xiao Y, Huang B, He B, et al. Surface morphology and microstructure evolution of trace titanium and yttrium in W-K-Mo-Ti-Y alloys under transient heat loads [J]. Int. J. Refract. Met. Hard Mater., 2018, 75: 299
77	Chookajorn T, Park M, Schuh C A. Duplex nanocrystalline alloys: Entropic nanostructure stabilization and a case study on W-Cr [J]. J. Mater. Res., 2015, 30: 151
78	Park M, Schuh C A. Accelerated sintering in phase-separating nanostructured alloys [J]. Nat. Commun., 2015, 6: 6858 doi: 10.1038/ncomms7858 pmid: 25901420
79	Tang F W, Liu X M, Wang H B, et al. Solute segregation and thermal stability of nanocrystalline solid solution systems [J]. Nanoscale, 2019, 11: 1813 doi: 10.1039/c8nr09782h pmid: 30631871
80	Du W L, Hou C, Li Y R, et al. Effect of addition of Cr and Sc on high-temperature stability of grain structure in W-based alloys [J]. Acta Metall. Sin., 2024, DOI: 10.11900/0412.1961.2024.00052
80	杜文力, 侯超, 李昱嵘等. Cr和Sc元素对钨基合金晶粒组织高温稳定性的影响 [J]. 金属学报, 2024, DOI: 10.11900/0412.1961.2024.00052
81	Wu Y C, Hou Q Q, Luo L M, et al. Preparation of ultrafine-grained/nanostructured tungsten materials: an overview [J]. J. Alloys Compd., 2019, 779: 926
82	Zhao Z H, Yao G, Luo L M, et al. Anisotropy and stability of the mechanical properties of the W alloy plate reinforced with Y-Zr-O particles and prepared by a wet chemical method [J]. Int. J. Refract. Met. Hard Mater., 2021, 99: 105597
83	Wang M M, Xie Z M, Deng H W, et al. Thermal shock fatigue behaviors of various W-0.5 wt%ZrC materials under repetitive transient heat loads [J]. J. Nucl. Mater., 2020, 534: 152152
84	Feng F, Lian Y Y, Liu X, et al. Transient thermal shock performance of sintered W-TaC by SPS [J]. Rare Met. Mater. Eng., 2017, 46: 3544
84	封范, 练友运, 刘翔等. SPS烧结W-TaC的耐瞬态热冲击性能 [J]. 稀有金属材料与工程, 2017, 46: 3544
85	Feng F, Lian Y Y, Wang J B, et al. Mechanical properties and thermal shock performance of high-energy-rate-forged W-1%TaC alloy [J]. Crystals, 2022, 12: 1047
86	Tejado E, Martin A, Pastor J Y. Effect of Ti and TiC alloyants on the mechanical properties of W-based armour materials [J]. J. Nucl. Mater., 2019, 514: 238 doi: 10.1016/j.jnucmat.2018.12.001
87	Tan X Y, Li P, Luo L M, et al. Effect of second-phase particles on the properties of W-based materials under high-heat loading [J]. Nucl. Mater. Energy, 2016, 9: 399
88	Yao G, Tan X Y, Luo L M, et al. Surface damage evolution during transient thermal shock of W-2 vol%Y₂O₃ composite material in different surfaces [J]. Fusion Eng. Des., 2019, 139: 86
89	Shen T L, Dai Y, Lee Y. Microstructure and tensile properties of tungsten at elevated temperatures [J]. J. Nucl. Mater., 2016, 468: 348
90	Yao G, Zhao Z H, Luo L M, et al. Damage evolutions of completely recrystallized W-Y₂O₃ composite evaluated using the dual effects of electron beam thermal shock and helium ion irradiation [J]. Mater. Chem. Phys., 2021, 271: 124947
91	Lv Y Q, Han Y, Zhao S Q, et al. Nano-in-situ-composite ultrafine-grained W-Y₂O₃ materials: Microstructure, mechanical properties and high heat load performances [J]. J. Alloys Compd., 2021, 855: 157366
92	Lv Y Q, Fan Y, Zhao S Q, et al. The microstructure evolution, damage behavior and failure analysis of fine-grained W-Y₂O₃ composites under high transient thermal shock [J]. Int. J. Refract. Met. Hard Mater., 2022, 107: 105905
93	Chen Z, Yang J J, Zhang L, et al. Effect of La₂O₃ content on the densification, microstructure and mechanical property of W-La₂O₃ alloy via pressureless sintering [J]. Mater. Charact., 2021, 175: 111092
94	Nogami S, Hasegawa A, Fukuda M, et al. Mechanical properties of tungsten: Recent research on modified tungsten materials in Japan [J]. J. Nucl. Mater., 2021, 543: 152506
95	Zhang X X, Yan Q Z, Yang C T, et al. Microstructure, mechanical properties and bonding characteristic of deformed tungsten [J]. Int. J. Refract. Met. Hard Mater., 2014, 43: 302
96	Shirokova V, Laas T, Ainsaar A, et al. Comparison of damages in tungsten and tungsten doped with lanthanum-oxide exposed to dense deuterium plasma shots [J]. J. Nucl. Mater., 2013, 435: 181
97	Zhang X X, Yan Q Z. Morphology evolution of La₂O₃ and crack characteristic in W-La₂O₃alloy under transient heat loading [J]. J. Nucl. Mater., 2014, 451: 283
98	Gaudio P, Montanari R, Pakhomova E, et al. W-1%La₂O₃ submitted to a single laser pulse: effect of particles on heat transfer and surface morphology [J]. Metals, 2018, 8: 389
99	Chen Z, Qin M L, Yang J J, et al. Thermal stability and grain growth kinetics of ultrafine-grained W with various amount of La₂O₃ addition [J]. Metall. Mater. Trans., 2020, 51A: 4113
100	Kanpara S, Khirwadkar S, Belsare S, et al. Fabrication of tungsten & tungsten alloy and its high heat load testing for fusion applications [J]. Mater. Today: Proc., 2016, 3: 3055
101	Zhao M Y, Zhou Z J, Zhong M, et al. Thermal shock behavior of fine grained W-Y₂O₃ materials fabricated via two different manufacturing technologies [J]. J. Nucl. Mater., 2016, 470: 236
102	Zhou Z J, Tan J, Qu D D, et al. Basic characterization of oxide dispersion strengthened fine-grained tungsten based materials fabricated by mechanical alloying and spark plasma sintering [J]. J. Nucl. Mater., 2012, 431: 202
103	Yao G, Chen H Y, Luo L M, et al. Enhanced thermal-mechanical properties of rolled tungsten bulk material reinforced by in situ nanosized Y-Zr-O particles [J]. Nucl. Eng. Technol., 2024, 56: 2141
104	Dong Z, Ma Z Q, Liu Y C. Accelerated sintering of high-performance oxide dispersion strengthened alloy at low temperature [J]. Acta Mater., 2021, 220: 117309
105	Liu Z, Yan S, Luo L M, et al. Effect of Hf content on microstructure and properties of ultrafine W-Y₂O₃ composites prepared by wet chemical method [J]. Chin. J. Nonferrous Met., 2024, 34: 125
105	刘祯, 颜硕, 罗来马等. Hf含量对湿化学法制备超细W-Y₂O₃复合材料显微组织与性能的影响 [J]. 中国有色金属学报, 2024, 34: 125
106	Zhang X X, Gong Z, Huang J J, et al. Thermal shock resistance of tungsten with various deformation degrees under transient high heat flux [J]. Mater. Res. Express, 2020, 7: 066503
107	Xie Z M, Miao S, Zhang T, et al. Recrystallization behavior and thermal shock resistance of the W-1.0 wt%TaC alloy [J]. J. Nucl. Mater., 2018, 501: 282
108	Liu X, Lian Y Y, Chen L, et al. Experimental and numerical simulations of ELM-like transient damage behaviors to different grade tungsten and tungsten alloys [J]. J. Nucl. Mater., 2015, 463: 166
109	He C Y, Feng F, Wang J B, et al. Improving the mechanical properties and thermal shock resistance of W-Y₂O₃ composites by two-step high-energy-rate forging [J]. Int. J. Refract. Met. Hard Mater., 2022, 107: 105883
110	Chen L Q, Huang B, Yang X L, et al. High thermal shock resistance realized by Ti/TiH₂ doped tungsten-potassium alloys [J]. J. Alloys Compd., 2019, 780: 388
111	Lian Y Y, liu X, Cheng Z K, et al. Thermal shock performance of CVD tungsten coating at elevated temperatures [J]. J. Nucl. Mater., 2014, 455: 371
112	Zhang X X, Yan Q Z. The thermal crack characteristics of rolled tungsten in different orientations [J]. J. Nucl. Mater., 2014, 444: 428

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