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  4. 锆合金第二相研究述评(Ⅰ):Zircaloys合金

中国有色金属学报, 2012, 22(6): 1594-1604.

锆合金第二相研究述评(Ⅰ):Zircaloys合金

柴林江 1, , 栾佰峰 2, , 周宇 3, , 邱日盛 4, , 陈建伟 5,

1.重庆大学材料科学与工程学院,重庆400044

2.重庆大学材料科学与工程学院,重庆400044

3.重庆大学材料科学与工程学院,重庆400044

4.重庆大学材料科学与工程学院,重庆400044

5.重庆大学材料科学与工程学院,重庆400044

基金项目:   中央高校基本科研业务费专项资金资助项目(CDJZR10130008;CDJXS10132201)   教育部新世纪优秀人才支持计划资助项目(NCET-08-0606)  

关键词： Zircaloys合金 , Laves相 , Zr-Fe-Ni粒子 , Zr-Fe-Cr粒子

Review of second phase particles on zirconium alloys (Ⅰ): Zircaloys

回顾了国内外近几十年来关于Zircaloys合金中第二相粒子本征特征(晶体结构、成分、形状、亚结构等)的相关研究工作.Zircaloys合金中的Zr-Fe-Ni粒子只有一种,即C16(BCT,Al2Cu)型Zr2(Fe,Ni) Zintl相.而Zr-Fe-Cr 粒子主要有两种:一种是C14(HCP,MgZn2)型Zr(Fe,Cr)2 Laves相,另一种是C15(FCC,MgCu2)型Zr(Fe,Cr)2 Laves 相,这些Laves相内部均可见层错结构.归纳总结出形成温度决定论、n(Fe)/n(Cr)决定论、价电子/原子比决定论3种理论,用于解释Zr(Fe,Cr)2粒子形成稳定结构的原因.常规加工工艺下,在Zircaloys合金成分范围内,Sn完全固溶于a-Zr基体,不会参与形成析出相,Fe、Cr,Ni一般也不会单独与Zr形成Zr-Fe、Zr-Cr、Zr-Ni粒子.

参考文献

[1] 刘建章 .国内核动力堆用锆合金的研究动向[J].稀有金属材料与工程,1990,19(06):32-35.
[2] KRUGER R M;ADAMSON R B;BRENNER S S .Effects of microchemistry and precipitate size on nodular corrosion resistance of zircaloy-2[J].Journal of Nuclear Materials,1992,189:193-200.
[3] 周邦新 .锆合金中的疖状腐蚀问题[J].核科学与工程,1993,13(01):51-58.
[4] RUDLING P;WIKMARK G;LEHTINEN B;PETTERSSON H.Impact of second phase particles on BWR Zr-2 corrosion and hydriding Performance[A].West Conshohocken:ASTM International,2000:678-706.
[5] GARZAROLLI F;RUHMANN H;van SWAM L.AIternative Zr alloys with irradiation resistant precipitates for high bumop BWR application[A].West Conshohocken:ASTM International,2002:119-132.
[6] GOLL W;RAY I.The behavior of intermetallic precipitates in highly irradiated BWR LTP cladding[A].West Conshohocken:ASTM International,2002:80-95.
[7] SABOL G.ZIRLO-An alloy development success[A].West Conshohocken:ASTM International,2005:3-24.
[8] SABOL G;KILP G;BALFOUR M;ROBERTS E.Development of a cladding alloy for high bumup[A].Philadelphia:ASTM International,1989:227-244.
[9] MARDON J;CHARQUET D;SENEVAT J.Influence of composition and fabrication process on out-of-pile and in-pile properties of M5 alloy[A].West Conshohocken:ASTM International,2000:505-524.
[10] NIKULINA A;MARKELOV V;PEREGUD M;BIBILASHVILI Y K,KOTREKHOV V A,LOSITSKY A F,KUZMENKO N V,SHEVNIN Y P,SHAMARDIN V K,KOBYLYANSKY G P,NOVOSELOV A E.Zirconium alloy E635 as a material for fuel rod cladding and other components of VVER and RBMK cores[A].West Conshohocken:ASTM International,1996:785-804.
[11] 李中奎,刘建章,朱梅生.合金元素对Zr-Sn-Fe-Cr-Nb合金性能的影响[J].稀有金属材料与工程,1996(05):43-48.
[12] 朱梅生;刘建章;李中奎;宋启忠 .8#新锆合金的组织与耐蚀性能的研究[J].稀有金属材料与工程,1996,25(04):36-40.
[13] 李中奎,刘建章,李佩志.新锆合金在两种不同介质中的耐蚀行为[J].稀有金属材料与工程,1999(02):101-104.
[14] OSTBERG G .Determination of the composition of the second phase in zirealoy[J].Journal of Nuclear Materials,1962,7:103-106.
[15] VANDER SANDE J;BEMENT A .An Investigation of second phase particles in zircaloy-4 alloys[J].Journal of Nuclear Materials,1974,52:115-118.
[16] VITIKAINEN E;NENONEN P .Transmissien electron microscopy studies on intermetallies in some zirconium alloys[J].Journal of Nuclear Materials,1978,78:362-373.
[17] CHEMELLE P;KNORR D;VANDER SANDE J;PELLOUX R .Morphology and composifion of second phase particles in zircaloy-2[J].Journal of Nuclear Materials,1983,113:58-64.
[18] RAO P;WALKER J;KOCH E.Intermetallic particles in zircaloy-2 and zircaloy-4[A].San Jose:Calif,1977:183-193.
[19] ARIAS D;PALACIOS T;RURRILLO C .Composition of precipitates present in zircaloy-2 and-4[J].Journal of Nuclear Materials,1987,148:227-229.
[20] MENG X Y;NORTHWOOD D O .Second phase particles in zircaloy-2[J].Journal of Nuclear Materials,1989,168:125-136.
[21] VERSACI R .Polytype Structure of intermetallic precipitates in zircaloy-4 alloys[J].Journal of Nuclear Materials,1979,80:180-183.
[22] VERSACI R;IPOHORSKI M .Composition of Zr(Cr,Fe)2-type precipitates in zircaloy-2 and zircaloy-4[J].Journal of Nuclear Materials,1983,116:321-323.
[23] MENONI C;PALACIOS T;ARIAS D.Intermetallic precipitates in zircaloy-4 alloys[J].Solid to Solid Phase Transformations,1981:763-767.
[24] KRASEVEC V .Transmission electron microscopy study of second-phese particles in zircaloy-2[J].Journal of Nuclear Materials,1981,98:235-237.
[25] KUWAE R;SATO K;HIGASHINAKAGAWA E;KAWASHIMA J NAKAMURA S I .Mechanism of zircaloy nodular corrosion[J].Journal of Nuclear Materials,1983,119:229-239.
[26] BANGARU N V .An investigation of the microstructures of heat-trested zircaloy-4[J].Journal of Nuclear Materials,1985,131:280-290.
[27] MENG X Y;NORTHWOOD D O .Intermetallic precipitates in zircaloy-4[J].Journal of Nuclear Materials,1985,132:80-87.
[28] MENG X Y;NORTHWOOD D O .A TEM study of the C15 type Zr(Cr,Fe)2 Laves phase in zircaloy-4[J].Journal of Nuclear Materials,1985,136:83-90.
[29] YANG W J S;TUCKER R P;CHENG B;ADAMSON R B .Precipitates in zircaloy:Identification and the effects of irradiation and thermal treatment[J].Journal of Nuclear Materials,1986,138:185-195.
[30] 赵文金 .Zr-4合金中第二相的研究[J].核动力工程,1991,12(05):66-72.
[31] YANG W J S;ADAMSON R.Beta-quenched zircaloy-4:Effects of thermal aging and neutron irradiation[A].Philadelphia:ASTM International,1989:451-477.
[32] 杨晓林;周邦新;蒋有荣;李聪 .Zr-4合金中第二相Zr(Fe,Cr)2的电化学分离[J].核动力工程,1994,15(01):79-83.
[33] 周邦新;杨晓林 .热处理对Zr-4合金中第二相结构和成份的影响[J].核动力工程,1997,18(06):511-516.
[34] 周邦新;李聪;黄德诚 .Zr(Fe,Cr)2金属间化合物的氧化[J].核动力工程,1993,14(02):149-153.
[35] WILLEY L A;MARGOLIN H.Metals handbook (Vol.8):Metallography,structure and phase diagrams[M].Metals Park,Ohio:American Society for Metals,1973:293-295.
[36] SHEN Y S;PAASCHE O G .On the transformation of ZrCr2[J].Transactions of the Metallurgical Society of AIME,1968,242:2241-2242.
[37] SHALTIEL D;JACOB I;DAVIDOV D .Hydrogen absorption and desorption properties of AB2 Laves-phase pseudobinary compounds[J].Journal of the Less-Common Metals,1977,53:117-131.
[38] MALAKHOVA T O;GUSEVA L N .Zirconium comer of the Zr-Cu-Cr-Fe phase-diagram[J].Russian Metallurgy,1980,5:221-224.
[39] ELLIOTT R P;ROSTOKER W .The occurrence of Laves-type phases among transition elements[J].Transactions of the American Society for Metals,1958,50:617-633.
[40] HUANG K;TSAl C .The effect of heat treatment on the microstructure and the corrosion resistance of zircaloy-4 in 450℃ steam[J].Journal of Nuclear Materials,1985,136:16-29.
[41] KAI J J;HUANG W I;CHOU H Y .The microstructural evolution of zircaloy-4 subjected to proton irradiation[J].Journal of Nuclear Materials,1990,170:193-209.
[42] CHARQUET D;HAHN R;ORTLIEB E;GROS J P,WADIER J E.Solubility limits and formation of intermtallic precipitates in ZrSnFeCr alloys[A].Philadelphia:ASTM International,1989:405-422.
[43] GARZAROLLI F;STEHLE H;STEINBERG E.Behavior and properties of Zircaloys in power reactors:A short review of pertinent aspects in LWR fuel[A].West Conshohocken:ASTM International,1996:12-32.
[44] EUCKEN C;FINDEN E T;TRAPP-PRITSCHING S;WEIDINGER H G.Influence of chemical composition on uniform corrosion of zirconium-base alloys in autoclave tests[A].Philadelphia:ASTM International,1989:113-127.
[45] RUHMANN H;MANZEL R;SELL H;CHARQUET D.In-BWR and out-of-pile nodular corrosion behavior of Zry-2/4type melts with varying Fe,Cr,and Ni content and varying process history[A].West Conshohocken:ASTM International,1996:865-888.
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