研究论文

Zr ODS FeCrAl合金在550Pb-Bi熔液中的腐蚀行为

  • 张晓晨 ,
  • 李静 ,
  • 李长记 ,
  • 熊良银 ,
  • 刘实
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  • 1 中国科学院金属研究所 师昌绪先进材料创新中心 沈阳 110016
    2 中国科学技术大学 材料科学与工程学院 沈阳 110016
    3 中国科学院金属研究所 中国科学院核用材料与安全评价重点实验室 沈阳 110016
    4 中国科学院金属研究所 沈阳材料科学国家研究中心 沈阳 110016
张晓晨,女,1998年生,硕士生
李 静,jingli@imr.ac.cn,主要从事核用结构材料的研究

收稿日期: 2023-12-15

  修回日期: 2024-01-27

  网络出版日期: 2024-05-13

基金资助

国家原子能机构核材料技术创新中心基金项目(ICNM-2023-YZ-03)

Corrosion Behavior of ODS FeCrAl Alloys Containing Zr Exposed to Lead-Bismuth Eutectic at 550 oC

  • ZHANG Xiaochen ,
  • LI Jing ,
  • LI Changji ,
  • XIONG Liangyin ,
  • LIU Shi
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  • 1 Shi -changxu Innovation Center for Advanced Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China
    2 School of Materials Science and Engineering, University of Science and Technology of China, Shenyang 110016, China
    3 CAS Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China
    4 Shenyang National Laboratory for Materials Science, Institute of Metals Research, Chinese Academy of Sciences, Shenyang 110016, China
LI Jing, professor, Tel: (024)83970760, E-mail: jingli@imr.ac.cn

Received date: 2023-12-15

  Revised date: 2024-01-27

  Online published: 2024-05-13

Supported by

Research Fund of Nuclear Materials of China Atomic Energy Authority(ICNM-2023-YZ-03)

摘要

结构材料与液态Pb-Bi熔液的相容性是铅冷快堆发展应用亟待解决的关键问题,氧化物弥散强化(ODS) FeCrAl合金是极具发展潜力的结构材料之一,但是对于高强度的含Zr ODS FeCrAl合金在液态Pb-Bi熔液中的研究较少。本工作利用SEM、XRD、EPMA等分析技术研究了粉末冶金法制备的含Zr ODS FeCrAl合金经550 ℃饱和氧液态Pb-Bi共晶合金浸泡10000 h后的腐蚀产物,研究了Zr、Ti、Al和O等元素含量对ODS FeCrAl合金耐Pb-Bi腐蚀性能的影响。结果表明,由于Zr元素在氧化初期抑制Al与O元素结合、阻碍Al元素向外扩散,使得含Zr ODS FeCrAl合金表面无法生成连续、保护性的Al2O3薄膜,腐蚀产物主要由薄的Al2O3膜和疖状的Fe的多层氧化物组成。疖状氧化物的分布和形貌受含Zr ODS FeCrAl合金中Ti、Al和O含量的影响。增加含Zr ODS FeCrAl合金中的O含量,会使Y-Zr-O纳米强化相高密度析出,基体中对Al2O3薄膜有不利影响的Zr含量降低,进而使疖状氧化物的数量、厚度及表面横向尺寸降低。在ODS FeCrAl合金中添加Ti元素,其对合金腐蚀行为的影响类似于Zr元素,可促进合金表面疖状氧化物数量增加。(4.0%~5.5%)Al的添加不能阻止含Zr ODS FeCrAl合金表面上生成Fe的氧化产物。

本文引用格式

张晓晨 , 李静 , 李长记 , 熊良银 , 刘实 . 含Zr ODS FeCrAl合金在550Pb-Bi熔液中的腐蚀行为[J]. 金属学报, 2025 , 61(9) : 1320 -1334 . DOI: 10.11900/0412.1961.2023.00489

Abstract

Lead-cooled fast reactor (LFR) is one of the most promising reactor types among the six reactor concepts outlined in the Technology Roadmap for Generation IV Nuclear Energy Systems. Lead-bismuth eutectics (LBEs) are often used as coolants for LFRs because of their excellent economy and safety. However, structural materials are eroded by high-density LBEs at high temperatures. The compatibility between LBE and structural materials is a key problem that must be urgently solved for the development and application of LFRs. Due to the pinning of dislocations and grain boundaries as well as capture of displaced atoms and helium bubbles by oxide nanoparticles, oxide dispersion strengthened (ODS) alloys exhibit outstanding high-temperature mechanical properties and swelling resistance under irradiation. Fe-based ODS alloys have emerged as candidates for cladding tubes and structural materials in advanced reactors. A protective alumina scale can be formed on the alloy surface by adding Al to ODS alloys, which prevents the further penetration of LBEs into the alloy substrate. However, Y-Al-O complex-oxide nanoparticles with a slightly larger size compared to Y-Ti-O complex nanoparticles (in ODS FeCr alloy) are also formed in the alloy, leading to a slight decrease in the high-temperature strength of ODS FeCrAl alloys. It is known that adding a small amount of Zr to ODS FeCrAl alloys is an effective strategy to compensate for the decrease of mechanical properties caused by the coarseness of oxide nanoparticles, as numerous small-sized Y-Zr-O complex nanoparticles would preferentially precipitate instead of Y-Al-O complex nanoparticles. Thus far, studies on the corrosion behavior and corresponding mechanism of ODS FeCrAl alloys containing Zr in LBEs have been scarce. In this work, ODS FeCrAl alloys containing Zr were prepared via powder metallurgy. After the alloys were corroded by an oxygen-saturated static liquid LBE at 550 oC for 10000 h, its corrosion products were characterized by SEM, XRD, and EPMA. The effects of Zr, Ti, Al, and O contents on the corrosion resistance of ODS FeCrAl alloys were studied. Due to the combination of Zr and O and its interference with the outward diffusion of Al at the initial stage of oxidation, no continuous, protective aluminum oxide scale was formed on the surface of the ODS FeCrAl alloys. The corrosion products were mainly composed of thin alumina scale and multilayer oxide nodules, and no peeling of oxidation products was observed on any of the specimens. Further, it was revealed that the outer layer of these oxide nodules was composed of Fe3O4 with a magnetite phase, the inner layer was composed of spinel FeCr2O4 and Fe(Cr, Al)2O4, and the internal oxidation zone (IOZ) contained the oxide of Al and Cr. In addition, the distribution and morphology of oxide nodules were also affected by the contents of Ti, Al, and O in the alloys. With an increase in O content, high-density Y-Zr-O complex nanoparticles precipitated in the ODS FeCrAl alloys containing Zr, which led to a reduction in the content of residual Zr in the substrate. Consequently, the Zr content, which adversely affected the formation of alumina scale, was reduced, and the quantity, thickness, and surface transverse dimension of oxide nodules decreased. Introducing Ti into the ODS FeCrAl alloys containing Zr was also found to be unfavorable to the formation of the alumina scale as its impact on corrosion behavior was similar to that of Zr. With the addition of Ti, an increased number of oxide nodules were formed on the surface of Zr-containing ODS FeCrAl alloys. Because the addition of (4.0%-5.5%)Al does not prevent the formation of Fe-rich oxide nodules on the ODS FeCrAl alloys containing approximately 0.3%Zr, it is necessary to further increase the Al content in the matrix to obtain a continuous alumina scale.

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