Ar離子輻照對(duì)Zr-0.75Sn-1Nb-0.35Fe-0.15Cr合金顯微組織和耐腐蝕性能的影響

doi:10.12442/j.issn.1002-185X.20230206

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Ar離子輻照對(duì)Zr-0.75Sn-1Nb-0.35Fe-0.15Cr合金顯微組織和耐腐蝕性能的影響
DOI:
                        10.12442/j.issn.1002-185X.20230206
                    
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作者單位:上海大學(xué)
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中圖分類號(hào):TL341
基金項(xiàng)目:國(guó)家重點(diǎn)基礎(chǔ)研究發(fā)展計(jì)劃（973計(jì)劃）（2022YFB1902400）,國(guó)家自然科學(xué)基金項(xiàng)目（面上項(xiàng)目，重點(diǎn)項(xiàng)目，重大項(xiàng)目）（52201079）

Effect of Ar Ion Irradiation on Microstructure and Corrosion Resistance of Zr-0.75Sn-1Nb-0.35Fe-0.15Cr Alloy

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Shanghai University

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通過(guò)熔煉、熱軋、冷軋和退火等工藝制備了Zr-0.75Sn-1Nb-0.35Fe-0.15Cr（wt.%）合金板狀樣品，采用靜電加速器在300 ℃下對(duì)樣品進(jìn)行注量為1.02×1015和5.1×1015 ions/cm2（對(duì)應(yīng)輻照損傷劑量分別為1和5 dpa）的Ar+輻照，然后將未輻照和輻照樣品置于360 ℃/18.6 MPa/0.01 M LiOH水溶液中腐蝕90 d，利用掃描電子顯微鏡和透射電子顯微鏡表征分析了輻照前后合金基體顯微組織和腐蝕后氧化膜截面顯微組織。結(jié)果表明，輻照前Zr-0.75Sn-1Nb-0.35Fe-0.15Cr合金為完全再結(jié)晶組織，晶粒呈等軸晶，第二相主要為fcc和hcp結(jié)構(gòu)的Zr(Fe,Cr,Nb)2，尺寸主要在50~100 nm范圍內(nèi)；輻照后，合金內(nèi)形成了型位錯(cuò)環(huán)，第二相發(fā)生了完全非晶化，但未發(fā)現(xiàn)第二相中元素向基體擴(kuò)散現(xiàn)象。腐蝕90 d后，輻照樣品的氧化膜厚度小于未輻照樣品，說(shuō)明Ar+輻照在一定程度上降低了合金腐蝕初期的腐蝕速率。分析認(rèn)為，Ar+輻照能延緩氧化膜顯微組織的演化，降低氧化膜中的等軸晶占比和裂紋數(shù)量，同時(shí)輻照誘導(dǎo)的非晶化第二相的氧化更慢，使氧化膜更具保護(hù)性，從而降低合金腐蝕速率。

Abstract:

Zr-0.75Sn-1Nb-0.35Fe-0.15Cr (wt.%) alloy plates were prepared by smelting, hot rolling, cold rolling and annealing techniques successively. The samples were then irradiated on an electrostatic accelerator with Ar+ to a fluence of 1.02×1015 and 5.1×1015 ions/cm2 (corresponding to 1 and 5 dpa, respectively) at 300 ℃. Both the unirradiated and irradiated samples were exposed to 360 ℃/18.6 MPa/0.01 M LiOH aqueous solution for 90 d. The microstructures of the alloy matrix before and after irradiation and the oxide film formed after corrosion were characterized by scanning electron microscope and transmission electron microscope. The results showed that before irradiation the alloy was fully recrystallized and the grains were equiaxed. The second phase particles were mainly Zr(Fe,Cr,Nb)2 with a fcc or hcp structure, and their size was within the range of 50~100 nm. After irradiation, -type dislocation loops were observed in the irradiated region of the alloy, and the second phase particles were completely amorphous, but the element diffusion from the second phase particles to the matrix was not found. After 90-d corrosion, the oxide film thickness of the irradiated samples was smaller than that of the unirradiated sample, indicating that Ar+ irradiation decreased the corrosion rate of the alloy to some extent at early stage of corrosion. This can be explained by the fact that Ar+ irradiation could delay the microstructural evolution of oxide film, including reducing the proportion of equiaxed grains and the number of cracks in the oxide film, as well as slowing down the oxidation of amorphous second phase particles induced by irradiation, thus enhancing the protectiveness of the oxide film.

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顧志遠(yuǎn),吳悅,林曉冬,姚美意,胡麗娟,梁雪,李毅豐,彭劍超,謝耀平,周邦新. Ar離子輻照對(duì)Zr-0.75Sn-1Nb-0.35Fe-0.15Cr合金顯微組織和耐腐蝕性能的影響[J].稀有金屬材料與工程,2024,53(6):1642~1653.[Gu Zhiyuan, Wu Yue, Lin Xiaodong, Yao Meiyi, Hu Lijuan, Liang Xue, Li Yifeng, Peng Jianchao, Xie Yaoping, Zhou Bangxin. Effect of Ar Ion Irradiation on Microstructure and Corrosion Resistance of Zr-0.75Sn-1Nb-0.35Fe-0.15Cr Alloy[J]. Rare Metal Materials and Engineering,2024,53(6):1642~1653.]
DOI：10.12442/j. issn.1002-185X.20230206

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收稿日期:2023-04-12
最后修改日期:2023-07-31
錄用日期:2023-08-09
在線發(fā)布日期: 2024-06-24
出版日期: 2024-06-17

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