Research and Development of Alloy Modified Tungsten-based Materials

doi:10.3901/JME.2018.08.117

Abstract

Abstract: Development of controlled nuclear fusion energy is an effective solution to solve the problem of future energy. In recent years many experimental studies home and abroad find that pure tungsten has many advantages, such as high melting point, high heat conductivity, low physical sputtering rate, low tritium retention and low swelling, etc. Applied in extreme environments of nuclear fusion reactors, the material requires good overall properties such as oxidation resistance, mechanical properties, anti-irradiation properties, etc. However there are also some problems to be solved. For example, lower oxidation resistance, low recrystallization temperature, high ductile-brittle transition temperature and irradiation sensitivity. Therefore W-based materials' properties were improved via doping alloying elements or stable dispersed phases and fabricating ultra-fine grain tungsten, etc. Alloying is one of the most common methods to improve the performance of tungsten-based materials. This paper summarizes the research results in recent years. This review focuses on the change of properties and the correlative mechanism of alloyed tungsten-based materials and analyzes the development trend in future.

Key words: alloying elements, nuclear fusion reactor, tungsten-matrix materials

CLC Number:

TG146

LUO Laima, HUANG Ke, ZAN Xiang, ZHU Xiaoyong, LI Ping, WU Yucheng. Research and Development of Alloy Modified Tungsten-based Materials[J]. Journal of Mechanical Engineering, 2018, 54(8): 117-128.

References

[1] 丁文艺,何海燕,潘必才. 磁约束可控热核聚变堆中的第一壁材料钨的研究状况和面临的若干问题[J]. 安徽师范大学学报, 2014, 37(4):314-319. DING Wenyi, HE Haiyan, PAN Bicai. The review and some problems about the first wall materials tungsten in magnetic confinement fusion reactor[J]. Journal of Anhui Normal University, 2014, 37(4):314-319.
[2] 朱玲旭,燕青芝,郎少庭,等. 钨基面向等离子体材料的研究进展[J]. 中国有色金属学报, 2012, 22(12):3522-3528. ZHU Lingxu, YAN Qingzhi, LANG Shaoting, et al. Research progress of tungsten-base materials as plasma facing materials[J]. The Chinese Joumal of Nonferrous Metals, 2012, 22(12):3522-3528.
[3] RIETH M, AKTTA J, ANTUSCH S. Recent progress in research on tungsten materials for nuclear fusion applications in Europe[J]. Journal of Nuclear Materials, 2013, 432(1-3):482.
[4] WURSTER S, BALUC N, BATTABYAL M, et al. Recent progress in R&D on tungsten alloys for divertor structural and plasma facing materials[J]. Journal of Nuclear Materials, 2013(442):S181-S189.
[5] 王爽,罗来马,赵美玲,等. 钨基材料强韧化技术的现状与发展趋势[J]. 稀有金属, 2015, 39(8):740-747. WANG Shuang, LUO Laima, ZHAO Meiling, et al. Current status and development trend of toughing technology of tungsten-based materials[J]. Chinese Journal of Rare Metals, 2015, 39(8):740-747.
[6] CALVO A, ORDÁS N, ITURRIZA I, et al. Manufacturing of self-passivating tungsten based alloys by different powder metallurgical routes[J]. Physica Scripta, 2016(167):14041-14046.
[7] STOTT F H, WOOD G C. Growth and adhesion of oxide scales on Al₂O₃-forming alloys and coatings[J]. Materials Science and Engineering, 1987(87):267-274.
[8] 王颖,张洋,张显程. 高温环境下应力变化与金属氧化行为的耦合模型[J]. 机械工程学报, 2015, 51(12):36-42. WANG Ying, ZHANG Yang, ZHANG Xiancheng. Analytical modeling on the stress evolution and oxidation process of metals in a high temperature[J]. Journal of Mechanical Engineering, 2015, 51(12):36-42.
[9] KOCH F, BOLT H. Self-passivating W-based alloys as plasma facing material for nuclear fusion[J]. Physica Scripta, 2007(T128):100-105.
[10] KOCH F, BOLT H, KÖPPL S. Self-passivating W-based alloys as plasma-facing materials[J]. Journal of Nuclear Materials, 2009(386-388):572-574.
[11] NAIDU S V N, SRIRAMAMURTHY A M, RAO P R. The Cr-W (Chromium-Tungsten) system[J]. Journal of Phase Equilibria, 1984, 5(3):289-292.
[12] TELU S, PATRA A, SANKARANARAYANA M, et al. Microstructure and cyclic oxidation behavior of W-Cr alloys prepared by sintering of mechanically alloyed nanocrystalline powders[J]. Int. Journal of Refractory Metals and Hard Materials, 2013(36):191-203.
[13] CALVO A, GARCÍA-ROSALES C, KOCH F, et al. Manufacturing and testing of self-passivating tungsten alloys of different composition[J]. Nuclear Materials and Energy, 2016, 9:422-429.
[14] KOCH F, BRINKMANN J, LINDIG S, et al. Oxidation behaviour of silicon-free tungsten alloys for use as the first wall material[J]. Physica Scripta, 2011(145):14-19.
[15] HUANG Xiaoxiao, LI Jinshan, HU Rui, Bet al. Evolution of oxidation in Ni-Cr-W alloy at 1100℃[J]. Rare Metal Materials and Engineering, 2010, 39(11):1908-1911.
[16] TELU S, MITRA R, PABI S K. High temperature oxidation behavior of W-Cr-Nb Alloys in the Temperature Range of 800-1200℃[J]. Int. Journal of Refractory Metals and Hard Materials, 2013(38):47-59.
[17] HONG S, FU C L. Phase stability and elastic moduli of Cr₂Nb by first-principles calculations[J]. Intermetallics, 1999(7):5-9.
[18] BOLT H, BARABASH V, FEDERICI G, et al. Plasma facing and high heat flux materials-needs for ITER and beyond[J]. Journal of Nuclear Materials, 2002(307-311):43-52.
[19] 武永红,李永堂,齐会萍,等. 基于铸辗连续成形的42CrMo铸造环坯高温力学性能及临界应变计算[J]. 机械工程学报, 2017, 53(6):45-52. WU Yonghong, LI Yongtang, QI Huiping, et al. High temperature mechanical properties and calculation of critical strain for 42CrMo ring blank based on casting-rolling forming[J]. Journal of Mechanical Engineering, 2017, 53(6):45-52.
[20] 朱玲旭,燕青芝,郎少庭,等. 钨基面向等离子体材料的研究进展[J]. 中国有色金属学报, 2012(12):3522-3528. ZHU Lingxu, YAN Qingzhi, LANG Shaoting, et al. Research progress of tungsten-base materials as plasma facing materials[J]. The Chinese Journal of Nonferrous Metals, 2012(12):3522-3528.
[21] LIU R, XIE Z M. Fabricating high performance tungsten alloys through zirconium micro-alloying and nano-sized yttria dispersion strengthening[J]. Journal of Nuclear Materials, 2014(451):35-39.
[22] XIE Z M, LIU R. Spark plasma sintering and mechanical properties of zirconium micro-alloyed tungsten[J]. Journal of Nuclear Materials, 2014(444):175-180.
[23] SAVOINI B, MARTÍNEZ J, MUÑOZ A, et al. Microstructure and temperature dependence of the microhardness of W-4V-1La₂O₃ and W-4Ti-1La₂O₃[J]. Journal of Nuclear Materials, 2013(442):S229-S232.
[24] MA Y, HAN Q F, ZHOU Z Y, et al. First-principles investigation on mechanical behaviors of W-Cr/Ti binary alloys[J]. Journal of Nuclear Materials, 2016(468):105-112.
[25] WANG Shuang, LUO Laima, ZHAO Meiling, et al. Microstructure and properties of TiN-reinforced W-Ti alloys prepared by spark plasma sintering[J]. Powder Technology, 2016(294):301-306.
[26] PINTSUK, UYTDENHOUWEN I. Thermo-mechanical and thermal shock characterization of potassium doped tungsten[J]. International Journal of Refractory Metals & Hard Materials, 2010, 25(5):661-668.
[27] HUANG Bo, XIAO Ye, HE Bo, et al. Effect of potassium doping on the thermal shock behavior of tungsten[J]. Int. Journal of Refractory Metals and Hard Materials, 2015(51):19-24.
[28] FUKUDA M, NOGAMI S H, HASEGAWA A, et al. Tensile properties of K-doped W-3%Re[J]. Fusion Engineering and Design, 2014(89):1033-1036.
[29] 吴玉程,林锦山,罗来马,等. 面向等离子体钨基材料的辐照损伤行为研究现状[J]. 机械工程学报, 2017, 53(8):25-34. WU Yucheng, LIN Jinshan, LUO Laima, et al. Irradiation damage behavior research status of tungsten-matrix materials facing plasma[J]. Journal of Mechanical Engineering, 2017, 53(8):25-34.
[30] LUO L M, SHI J, LIN J, et al. Microstructure and performance of rare earth element-strengthened plasma-facing tungsten material[J]. Sci. Rep., 2016, 6:32701.
[31] COTTRELL G A. Sigma phase formation in irradiated tungsten, tantalum and molybdenum in a fusion power plant[J]. Journal of Nuclear Materials, 2004(334):166-168.
[32] SCHMID K, RIEGER V, MANHARD A. Comparison of hydrogen retention in W and W/Ta alloys[J]. Journal of Nuclear Materials, 2012(426):247-253.
[33] DIAS M, MATEUS R, CATARINO N, et al. Synergistic helium and deuterium blistering in tungsten-tantalum composites[J]. Journal of Nuclear Materials, 2013(442):69-74.
[34] PARISH C M, WANG K, DOERNER R P, et al. Grain orientations and grain boundaries in tungsten nonotendril fuzz grown under divertor-like conditions[J]. Scripta Materialia, 2017(127):132-135.
[35] TOKITANI M, MASUZAKI S, KASAHARA H, et al. Initial growth phase of W-fuzz formation in ultra-long pulse helium discharge in LHD[EB/OL].[2016-12-26]. http://www.sciencedirect.com/science/article/pii/S2352179116300278.
[36] SINCLAIR G, TRIPATHI J K, DIWAKAR P K, et al. Structural evolution of tungsten surface exposed to sequential low-energy helium ion irradiation and transient heat loading[EB/OL].[2017-03-18]. http://www.sciencedirect.com/science/article/pii/S235217911630120X.
[37] LIU Lu, LIU Dongping, HONG Yi, et al. High-flux He irradiation effects on surface damages of tungsten under ITER relevant conditions[J]. Journal of Nuclear Materials, 2016(471):1-7.
[38] HATANO Y, AMI K, ALIMOV V K, et al. Deuterium retention in W and W-Re alloy irradiated with high energy Fe and W ions:Effects of irradiation temperature[J]. Nuclear Materials and Energy, 2016, 9:93-97.
[39] SUZUDO T, YAMAGUCHI M, HASEGAWA A. Stability and mobility of rhenium and osmium in tungsten:First principles study[J]. Modelling and Simulation in Materials Science and Engineering, 2014, 22(7):1-16.
[40] KHAN A, TEMMERMAN G D, MORGAN T W, et al. Effect of rhenium addition on tungsten fuzz formation in helium plasmas[J]. Journal of Nuclear Materials, 2016(474):99-104
[41] BALDWIN M J, DOERNER R P. Formation of helium induced nanostructure ‘fuzz’ on various tungsten grades[J]. Journal of Nuclear Materials, 2010(404):165-173.
[42] XU A, CHRISTIAN B, ARMSTRONG D E J, et al. Ion-irradiation-induced clustering in W-Re and W-Re-Os alloys:Acomparative study using atom probe tomography and nanoindentation measurements[J]. Acta Materialia, 2015(87):121-127.
[43] BECQUART C S, DOMAIN C. Solute-point defect interactions in bcc systems:Focus on first principles modelling in W and RPV steels[J]. Current Opinion in Solid State and Materials Science, 2012(16):115-125.