参照锆合金中的第二相成分,熔炼2种不同Fe/Cr比的Zr(Fe,Cr)<,2>(Fe/Cr=2和0.5)和ZrCr<,2>(Fe/Cr=0)3种试验合金,对它们进行压力.成分.温度(P-C-T)测试和吸放氢动力学测试.同时用XRD对360℃吸氢前后的样品进行物相分析.实验结果表明,这3种合金在50,200,360℃3个温度下,均有吸氢量随Fe/Cr比值的降低而增加的现象.另外,在360℃,4 MPa氢气气氛中测试时,这3种不同合金的可逆吸放氢量和吸放氢速度随Fe/Cr比的降低而增加.XRD测试表明,在360℃吸氢后并没有氢化物生成.
参考文献
| [1] | Charquet D;Hahn R.Zirconium in the Nuclear Industry:Eighth International Symposium[M].West Conshohocken,PA:ASTM International,1989:405. |
| [2] | Pettersson K;Bergqvist H.External Cladding Corrosion in Water Power Reactors[M].Vienna:International Atomic Energy Agency,1985:53. |
| [3] | Toffolon-Masclet C.;Brachet JC.;Jago G. .Studies of second phase particles in different zirconium alloys using extractive carbon replica and an electrolytic anodic dissolution procedure[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2002(2/3):224-231. |
| [4] | Toffolon-Masclet C;Barberis P;Brachet J C.Zirconium in the Nuclear Industry:Fourteenth International Symposium[M].West Conshohocken,PA:ASTM International,2004:81. |
| [5] | Hong HS.;Kim SJ.;Lee KS.;Moon JS. .Investigation on the oxidation characteristics of copper-added modified Zircaloy-4 alloys in pressurized water at 360 degrees C[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2001(2):113-119. |
| [6] | Etoh Y;Schimada S;Yasuda T.Zirconium in the Nuclear Industry:Eleventh International Symposium[M].West Conshohocken,PA:ASTM International,1996:825. |
| [7] | Tagstrom P;Limback M.Zirconium in the Nuclear Industry:Thirteenth International Symposium[M].West Conshohocken,PA:ASTM International,2002:96. |
| [8] | Barberis P;Ahlberg E.Zirconium in the Nuclear Industry:Thirteenth International Symposium[M].West Conshohocken,PA:ASTM International,2002:33. |
| [9] | Qian Shenghua .Windsor University Doctoral Dissertation[D].Canada:Windsor University,1989. |
| [10] | Douglas G Ivey .Windsor University Doctoral Dissertation[D].Canada:Windsor University,1985. |
| [11] | Adel Esayed .Windsor University Doctoral Dissertation[D].Canada:Windsor University,1993. |
| [12] | 姚美意;周邦新 .Thesis for Doctorate(博士论文)[D].上海:上海大学,2007. |
| [13] | 周邦新;杨晓林 .[J].核动力工程,1997,18(06):511. |
| [14] | 胡子龙.Hydrogen Storage Materials(贮氢材料)[M].北京:化学工业出版社,2003:49. |
| [15] | Kakiuchi K;Itagaki N;Furuya T.Zirconium in the Nuclear industry:Fourteenth International Symposium[M].West Conshohocken,PA:ASTM International,2004:349. |
| [16] | 姚美意,周邦新,李强,刘文庆,苗志,俞应华.合金成分对锆合金焊接区腐蚀时吸氢性能的影响[J].稀有金属材料与工程,2004(06):641-645. |
| [17] | Yao MY;Zhou BX;Li Q;Liu WQ;Chu YL .The effect of alloying modifications on hydrogen uptake of zirconium-alloy welding specimens during corrosion tests[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2006(2):195-201. |
| [18] | Rao E .General Electric Company Report 76 CRD[R].Calif:San Jose,1977. |
| [19] | 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. |
| [20] | 周邦新,姚美意,李强,夏爽,刘文庆,褚于良.Zr-Sn-Nb合金耐疖状腐蚀性能的研究[J].稀有金属材料与工程,2007(08):1317-1321. |
上一张
下一张
上一张
下一张
计量
- 下载量()
- 访问量()
文章评分
- 您的评分：
-
10%
-
20%
-
30%
-
40%
-
50%