氘含量对Zr-4合金显微组织和力学性能的影响*
收稿日期: 2015-05-17
网络出版日期: 2016-09-28
基金资助
* 国家自然科学基金项目21171018和51271021资助
EFFECTS OF DEUTERIUM CONTENT ON MICROSTRUCTURE AND MECHANICAL PROPERTIES OF Zr-4 ALLOY
Received date: 2015-05-17
Online published: 2016-09-28
Supported by
Supported by National Natural Science Foundation of China (Nos.21171018 and 51271021)
采用XRD, OM, BSE, SEM和显微硬度计等手段研究了氘含量对Zr-4合金显微组织及力学性能的影响. 结果表明, 随着氘含量(质量分数)从1.35%增加到2.21%, 氘化物数量增加, 其形态及分布也发生了显著变化: 在1.35%时, 主要以晶内针状氘化物析出为主; 随着氘含量增加, 晶界块状氘化物快速增长; 当氘含量进一步增加至2.21%时, 晶界块状氘化物开始相互衔接, 并逐渐向晶内生长. 在氘含量较高的样品表层, 有一定厚度的氘化物层形成, 且层内出现微裂纹. 所形成的氘化物以δ-氘化物为主, 而高氘含量样品表面有ε-氘化物出现. 样品心部至表面存在一定的硬度梯度, 且随着氘含量的增加, 样品的硬度增加, 其相应的硬度梯度增大. 随氘含量增加, 样品的屈服强度略有增加, 而抗压强度却显著下降, 由1.35%下的1176 MPa降低到了2.21%下的856 MPa. 抗压强度的降低与组织中微裂纹有关. 样品压缩后的裂纹主要沿晶界块状氘化物形成并扩展, 因此晶界块状氘化物是材料压缩性能下降的主要原因.
张诚 , 宋西平 , 刘敬茹 , 杨云 , 尤力 . 氘含量对Zr-4合金显微组织和力学性能的影响*[J]. 金属学报, 2016 , 52(12) : 1572 -1578 . DOI: 10.11900/0412.1961.2016.00193
Zirconium alloy has been employed widely in nuclear industry, yet the absorption of deuterium in zircaloy is considered to play a critical role in mechanical properties especially in high temperature under a loss of coolant accident (LOCA) and application for deuterium storage. However, little is known about the microstructure evolution of zircaloy during deuterium absorption. In this work, deuterium was charged into the sample at 900oC and different pressures, and the effects of deuterium content on microstructure and mechanical properties of Zr-4 alloy have been studied by means of OM, BSE, SEM, XRD, and hardness and compressive tests. The results showed that the amount of deuteride increased with the increase of deuterium content from 1.35% to 2.21%, accompanying with the morphology variations from intragranular deuteride needles to intergranular deuteride blocks, which formed an interlinked deuteride configuration and grew into equiaxed α-Zr grains. Deuteride layer was observed on the surface of sample at higher deuterium content with the micro-crack appeared within it. The mostly deuteride was δ-deuteride, and ε-deuteride was observed on sample surface with high deuterium content. There existed a hardness gradient from surface to center. With the increase of deuterium content, the hardness increased and hardness gradient became evident. With increasing deuterium content, the compressive yield strength of samples in creased slightly, but the compressive ultimate strength decreased greatly from 1176 MPa (1.35%) to 856 MPa (2.21%). The deceasing of compressive ultimate strength was probably related to the formation of micro-crack. The cracks nucleated and propagated within the intergranular deuteride blocks, which leads to the degradation of compressive ultimate strength.
Key words: zircaloy,; deuterium; content,; microstructure,; mechanical; property,; deuteride
| [1] | Zinkle S J, Was G S.Acta Mater, 2013; 61: 735 |
| [2] | Li Z K, Liu J Z, Xue X Y.Mat-China, 2007; 26(1): 6 |
| [2] | (李中奎, 刘建章, 薛祥义. 中国材料进展, 2007; 26(1): 6) |
| [3] | Northwood D O.Mater Des, 1985; 6: 58 |
| [4] | Motta A T, Yilmazbayhan A, Da Silva M J G, Comstock R J, Was G S, Busby J T, Gartner E, Peng Q, Jeong Y H, Park J Y.J Nucl Mater, 2007; 371: 61 |
| [5] | Yao M Y, Li S L, Zhang X, Peng J C, Zhou B X, Zhao X S, Shen J Y.Acta Metall Sin, 2011; 47: 865 |
| [5] | (姚美意, 李士炉, 张欣, 彭剑超, 周邦新, 赵旭山, 沈剑韵. 金属学报, 2011; 47: 865) |
| [6] | Sun G C, Zhou B X, Yao M Y, Xie S J, Li Q.Acta Metall Sin, 2012; 48: 1103 |
| [6] | (孙国成, 周邦新, 姚美意, 谢世敬, 李强. 金属学报, 2012; 48: 1103) |
| [7] | Allen T R, Konings R J M, Motta A T. Comprehensive Nuclear Materials. Oxford: Elsevier, 2012: 49 |
| [8] | Forgeron T, Brachet J C, Barcelo F, Castaing A, Hivroz J, Mardon J P, Bernaudat C.In: Sabol G P, Moan G D eds., Zirconium in the Nuclear Industry: Twelfth International Symposium, West Conshohocken, PA: ASTM International, 2000: 256 |
| [9] | Zinkle S J, Terrani K A, Gehin J C, Ott L J, Snead L L.J Nucl Mater, 2014; 448: 374 |
| [10] | Yang Y, Song X P, Zhang C.J Nucl Mater, 2015; 465: 97 |
| [11] | Zhao C, Song X P, Yang Y, Zhang B.Int J Hydrogen Energy, 2013; 38: 10903 |
| [12] | Yang Y, Song X P.Acta Metall Sin, 2016; 52: 100 |
| [12] | (杨云, 宋西平. 金属学报, 2016; 52: 100) |
| [13] | Sidhu S S, Murthy N S, Campos F P.Adv Chem Ser, 1963; 39: 87 |
| [14] | Zuzek E, Abriata J P, San-Martin A, Manchester F D.Bull Alloy Phase Diagrams, 1990; 11: 385 |
| [15] | Qin W, Kiran Kumar N A P, Szpunar J A, Kozinski J.Acta Mater, 2011; 59: 7010 |
| [16] | Carpenter G J C.J Nucl Mater, 1973; 48: 264 |
| [17] | Pshenichnikov A, Stuckert J, Walter M.Nucl Eng Des, 2015; 283: 33 |
| [18] | Yamanaka S, Yoshioka K, Uno M, Katsura M, Anada H, Matsuda T, Kobayashi S. J Alloys Compd#/magtechI#, 1999; 293-295: 23 |
| [19] | Kuroda M, Setoyama D, Uno M, Yamanaka S.J Alloys Compd, 2004; 368: 211 |
| [20] | Wang Z Y, Garbe U, Li H J, Studer A J, Harrison R P, Callaghan M D, Wang Y B, Liao X Z.Scr Mater, 2012; 67: 752 |
| [21] | Wang ZY, Garbe U, Li HJ, Harrison R P, Kaestner A, Lehmann E.Metall Mater Trans, 2014; 45B: 532 |
| [22] | Simpson L A, Cann C D.J Nucl Mater, 1979; 87: 303 |
| [23] | Kim Y S, Ahn S B, Cheong Y M.J Alloys Compd, 2007; 429: 221 |
| [24] | Shi S Q, Puls M P.J Nucl Mater, 1994; 208: 232 |
| [25] | Puls M P.Metall Trans, 1988; 19A: 1507 |
| [26] | Bai J B, Fran?ois D. J Nucl Mater, 1992; 187: 186 |
| [27] | Bai J B, Prioul C, Francois D.Metall Mater Trans, 1994; 25A: 1185 |
| [28] | Grange M, Besson J, Andrieu E.Metall Mater Trans, 2000; 31A: 679 |
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| 〈 |
|
〉 |