Research progress in irradiation damage of tungsten and tungsten alloys for nuclear fusion reactor

被引：0

作者：

Ding, Xiaoyu ^{[1
]}

Luo, Laima ^{[1
,3
]}

Huang, Limei ^{[1
]}

Luo, Guangnan ^{[2
]}

Li, Ping ^{[1
,3
]}

Wu, Yucheng ^{[1
,3
]}

机构：

[1] School of Materials Science and Engineering, Hefei University of Technology, Hefei

[2] Institute of Plasma Physics, Chinese Academic Sciences, Hefei

[3] Laboratory of Nonferrous Metal Material and Processing Engineering of Anhui Province, Hefei

来源：

Xiyou Jinshu/Chinese Journal of Rare Metals | 2015年 / 39卷 / 12期

关键词：

Nuclear fusion reactor; Plasma facing materials; Radiation damage; Tungsten;

D O I：

10.13373/j.cnki.cjrm.2015.12.012

中图分类号：

学科分类号：

摘要：

With the demand for energy growing rapidly, fossil fuel and other traditional energy resources which bring about serious environmental problems will soon dry up in the foreseeable future. Producing fusion energy by light nuclear fusion reaction is an important potential way to solve the energy problem of human. Recent researches on fusion reactor have made significant progress, and the resulting material problem has become a realistic problem due to that the materials in the reactor will face harsh working environment. Tungsten (W) is considered to be the primary candidate for plasma facing materials like first wall in future fusion reactors owing to its superiority to other materials including high melting point, high thermal conductivity, high density, low thermal expansion coefficient, low vapor pressure, low tritium inventory, low sputtering yield and high energy threshold for physical sputtering, etc. However, there are still serious challenges of brittleness for W and W alloys in the future application for fusion reactors. Defects induced by irradiation often lead to embrittlement of the material, thus shortening the service life of components. The defects will also interact with precious fusion fuel (such as tritium), leading to serious retention and permeation. Therefore, it is very necessary to study the radiation damage of W and W-based materials and it will be of great significance to delay irradiation defects through designing material composition/structure/organization. In order to provide a reference to researchers devoted to irradiation damage, irradiation damage status and the latest research progress of commercial W and advanced W alloys were reviewed in the paper. © Editorial Board of Chinese Journal of Rare Metals. All right reserved.

引用

页码：1139 / 1147

页数：8

共 39 条

[1]

Rieth M., Dudarev S.L., Gonzalez De Vicente S.M., Aktaa J., Ahlgren T., Antusch S., Armstronga D.E.J., Balden M., Baluco N., Barthe M.-F., Basuki W.W., Battabyal M., Becquart C.S., Blagoeva D., Boldyryeva H., Brinkmann J., Celino M., Ciupinski L., Correia J.B., De Backer A., Domain C., Gaganidze E., Garcia-Rosales C., Gibsona J., Gilbert M.R., Giusepponi S., Gludovatz B., Greuner H., Heinola K., Hoschen T., Hoffmann A., Holstein N., Koch F., Krauss W., Li H., Lindig S., Linke J., Linsmeier C.H.,

[2]

Pitts R.A., Carpentier S., Escourbiac F., Hirai T., Komarov V., Kukushkin A.S., Lisgo S., Loarte A., Merola M., Mittear R., Raffray A.R., Shimada M., Stangeby P.C., Physics basis and design of the ITER plasma-facing components, Journal of Nuclear Materials, 415, 1, (2011)

[3]

Raffray A.R., Nygren R., Whyte D.G., Abdel-Khalik S., Doerner R., Escourbiac F., Evans T., Goldston R.J., Hoelzer D.T., Konishi S., Lorenzetto P., Merola M., Neu R., Norajitra P., Pitts R.A., Rieth M., Roedig M., Rognlien T., Suzuki S., Tillack M.S., Wong C., High heat flux components-readiness to proceed from near term fusion systems to power plants, Fusion Engineering and Design, 85, 1, (2010)

[4]

Kurishita H., Matsuo S., Arakawa H., Narui M., Yamazaki M., Sakamoto T., Kobayashi S., Nakai K., Takida T., Takebe K., Kawai M., Yoshida N., High temperature tensile properties and their application to toughness enhancement in ultra-fine grained W-(0-1.5)wt% TiC, Journal of Nuclear Materials, 386-388, (2009)

[5]

Genc A., Coskun S., Ovecogglu M.L., Decarburization of TiC in Ni activated sintered W-xTiC (x=0, 5, 10, 15 wt%) composites and the effects of heat treatment on the microstructural and physical properties, International Journal of Refractory Metals and Hard Materials, 28, 3, (2010)

[6]

Genc A., Coskun S., Ovecogglu M.L., Microstructural characterizations of Ni activated sintered W-2wt% TiC composites produced via mechanical alloying, Journal of Alloys and Compounds, 497, 1-2, (2010)

[7]

Song G.M., Wang Y.J., Zhou Y., Thermomechanical properties of TiC particle-reinforced tungsten composites for high temperature applications, International Journal of Refractory Metals and Hard Materials, 21, 1-2, (2003)

[8]

Song G.M., Zhou Y., Wang Y.J., The microstructure and elevated temperature strength of tungsten-titanium carbide composite, Journal of Materials Science, 37, 16, (2002)

[9]

Song G.M., Wang Y.J., Zhou Y., The mechanical and thermophysical properties of ZrC/W composites at elevated temperature, Materials Science and Engineering: A, 334, 1-2, (2002)

[10]

Luo L.M., Luo Z.L., Li H., Luo G.N., Zan X., Wu Y.C., Current status and development trend on rare earth modified tungsten alloys, Chinese Journal of Rare Metals, 37, 6, (2013)

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