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钨涂层是最有希望的聚变堆偏滤器高热负荷面对等离子体材料.系统总结了钨涂层材料、连接及其制备研究进展,分析了钨涂层材料及其与热沉连接存在的问题,提出了偏滤器高热负荷面对等离子体钨涂层铁素体钢热沉材料(W/ODS)连续制备的发展方向,分析了钨涂层制备方法的优缺点,指出了电子束物理气相沉积(EBPVD)方法连续制备大面积的、显微结构可控的W/ODS的研发方向.

参考文献

[1] 李云凯,葛昌纯,赵哲,熊涛,刘翔.B4C涂层作为等离子体面对材料的一些性质[J].核科学与工程,2002(01):53-58.
[2] 张国兵,郭全贵,刘朗,史景利,宋进仁.SiC/C功能梯度材料的设计、制备及性能[J].宇航材料工艺,2006(z1):60-65.
[3] 凌云汉,李江涛,葛昌纯.聚变堆面向等离子体SiC/Cu梯度材料的制备与评价[J].北京科技大学学报,2001(03):257-261.
[4] 刘翔,谌继明,许增裕,邓颖,葛昌纯,李江涛.W/Cu梯度功能材料的高热负荷性能研究[J].核聚变与等离子体物理,2002(04):203-208.
[5] 凌云汉,白新德,周张键,李江涛,葛昌纯.面向等离子体W/Cu FGM的抗热冲击性能[J].稀有金属材料与工程,2004(08):819-822.
[6] Liu X;Zhang F;Tao SY;Cao YZ;Xu ZY .Research and development of plasma sprayed tungsten coating on graphite and copper substrates[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2007(0):1299-1303.
[7] Tamura S;Liu X;Tokunaga K;Tsunekawa Y;Okumiya M;Noda N;Yoshida N .High-temperature properties of joint interface of VPS-tungsten coated CFC[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2004(0):711-716.
[8] Maier H;Neu R;Greuner H;Hopf C;Matthews GF;Piazza G;Hirai T;Counsell G;Courtois X;Mitteau R .Tungsten coatings for the JET ITER-like wall project[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2007(0):1246-1250.
[9] Maier H.;Luthin J.;Balden M.;Lindig S.;Linke J.;Rohde V.;Bolt H. .Development of tungsten coated first wall and high heat flux components for application in ASDEX Upgrade[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2002(Pt.a):116-120.
[10] 宋书香,周张健,都娟,姚伟志,葛昌纯.不同界面对等离子喷涂钨结合强度的影响[J].稀有金属材料与工程,2007(10):1811-1814.
[11] Tokunaga K.;Miyamoto Y.;Takao Y.;Yoshida N.;Noda N. Kubota Y.;Sogabe T.;Kato T.;Plochl L.;Matsubara T. .Changes of composition and microstructure of joint interface of tungsten coated carbon by high heat flux[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2000(Pt.B):1121-1127.
[12] Liu X;Tamura S;Tokunaga K;Yoshida N;Noda N;Yang L;Xu Z .High heat flux properties of pure tungsten and plasma sprayed tungsten coatings[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2004(0):687-691.
[13] Missirlian M;Escourbiac F;Merola M;Durocher A;Bobin-Vastra I;Schedler B .Damage evaluation under thermal fatigue of a vertical target full scale component for the ITER divertor[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2007(b):1330-1336.
[14] Norajitra P;Boccaccini LV;Gervash A;Giniyatulin R;Holstein N;Ihli T;Janeschitz G;Krauss W;Kruessmann R;Kuznetsov V .Development of a helium-cooled divertor: Material choice and technological studies[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2007(b):1416-1421.
[15] Hua, Y.F.;Li, Z.X.;Zhang, X.;Du, J.H.;Huang, C.L.;Du, M.H. .Inter-diffusion analysis of joint interface of tungsten-rhenium couple[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2011(3):270-272.
[16] 华云峰,李争显,黄春良,杜继红,骆瑞雪.C/C复合材料表面双层辉光等离子制备铼涂层研究[J].稀有金属材料与工程,2012(11):2013-2016.
[17] 凌云汉,周张键,李江涛,杨大正,葛昌纯.超高压梯度烧结法制备W/Cu功能梯度材料[J].中国有色金属学报,2001(04):576-581.
[18] Bolt, H;Barabash, V;Krauss, W;Linke, J;Neu, R;Suzuki, S;Yoshida, N;ASDEX Upgrade Team .Materials for the plasma-facing components of fusion reactors[J].Journal of Nuclear Materials,2004(0):66-73.
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