Mechanical property and strengthening mechanism of ZrC nanoparticle dispersion-strengthened Mo containing FeCrAl alloys

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-07-23 DOI:10.1016/j.jnucmat.2024.155302

{"title":"Mechanical property and strengthening mechanism of ZrC nanoparticle dispersion-strengthened Mo containing FeCrAl alloys","authors":"","doi":"10.1016/j.jnucmat.2024.155302","DOIUrl":null,"url":null,"abstract":"<div><p>Poor mechanical strength at high temperature is the key problem to limit the application of FeCrAl alloys as the candidates for the accident tolerant fuel (ATF) cladding in LWRs. Fe-13Cr-5Al (wt %) alloys were strengthened by adding solid solution element Mo and nanosized ZrC particles, and the strengthening mechanism was assessed by microstructure characterizations including TEM and EBSD. Fe-13Cr-5Al-2Mo-1ZrC alloy has the highest ultimate tensile strength (UTS) and an acceptable ductility at each tested temperature (Room temperature, 400 °C or 800 °C). Especially at 800 °C, the UTS of Fe-13Cr-5Al-2Mo-1ZrC alloy is about 124 MPa, which is 125 % and 34.7 % higher than that of raw Fe-13Cr-5Al (55 MPa) and Fe-13Cr-5Al-1ZrC alloys (89 MPa), respectively. Fe-13Cr-5Al-2Mo-1ZrC alloy has the highest hardness of 306.3 HV, which is 12.8 % higher than that of Fe-13Cr-5Al and 3.7 % higher than that of Fe-13Cr-5Al-1ZrC alloys, respectively. Furthermore, Fe-13Cr-5Al-2Mo-1ZrC samples maintain high strength and favorable ductility after annealing at 1000 °C for 20 h indicating their superior thermal stabilities. The excellent mechanical properties and superior thermal stabilities of Fe-13Cr-5Al-2Mo-1ZrC alloy were not only attributed to the dispersion strengthen by nanosized ZrC particles, the solid solution strengthening by Mo elements, but also the grain refinement structure promoted by the synergistic effects of Mo and ZrC additions.</p></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":null,"pages":null},"PeriodicalIF":2.8000,"publicationDate":"2024-07-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Materials","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0022311524004045","RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"MATERIALS SCIENCE, MULTIDISCIPLINARY","Score":null,"Total":0}

引用次数: 0

Abstract

Poor mechanical strength at high temperature is the key problem to limit the application of FeCrAl alloys as the candidates for the accident tolerant fuel (ATF) cladding in LWRs. Fe-13Cr-5Al (wt %) alloys were strengthened by adding solid solution element Mo and nanosized ZrC particles, and the strengthening mechanism was assessed by microstructure characterizations including TEM and EBSD. Fe-13Cr-5Al-2Mo-1ZrC alloy has the highest ultimate tensile strength (UTS) and an acceptable ductility at each tested temperature (Room temperature, 400 °C or 800 °C). Especially at 800 °C, the UTS of Fe-13Cr-5Al-2Mo-1ZrC alloy is about 124 MPa, which is 125 % and 34.7 % higher than that of raw Fe-13Cr-5Al (55 MPa) and Fe-13Cr-5Al-1ZrC alloys (89 MPa), respectively. Fe-13Cr-5Al-2Mo-1ZrC alloy has the highest hardness of 306.3 HV, which is 12.8 % higher than that of Fe-13Cr-5Al and 3.7 % higher than that of Fe-13Cr-5Al-1ZrC alloys, respectively. Furthermore, Fe-13Cr-5Al-2Mo-1ZrC samples maintain high strength and favorable ductility after annealing at 1000 °C for 20 h indicating their superior thermal stabilities. The excellent mechanical properties and superior thermal stabilities of Fe-13Cr-5Al-2Mo-1ZrC alloy were not only attributed to the dispersion strengthen by nanosized ZrC particles, the solid solution strengthening by Mo elements, but also the grain refinement structure promoted by the synergistic effects of Mo and ZrC additions.

Abstract Image

查看原文

微信好友朋友圈 QQ好友复制链接

本刊更多论文

ZrC 纳米粒子分散强化含 Mo 的 FeCrAl 合金的力学性能和强化机理

高温下机械强度差是限制铁铬铝合金作为低温反应堆事故耐受燃料（ATF）包层候选材料应用的关键问题。通过添加固溶元素 Mo 和纳米级 ZrC 粒子，对 Fe-13Cr-5Al (wt%) 合金进行了强化，并通过 TEM 和 EBSD 等显微结构表征评估了强化机制。Fe-13Cr-5Al-2Mo-1ZrC 合金在每个测试温度（室温、400°C 或 800°C）下都具有最高的极限拉伸强度（UTS）和可接受的延展性。特别是在 800°C 时，Fe-13Cr-5Al-2Mo-1ZrC 合金的极限拉伸强度约为 124 兆帕，分别比未加工的 Fe-13Cr-5Al 合金（55 兆帕）和 Fe-13Cr-5Al-1ZrC 合金（89 兆帕）高 125% 和 34.7%。Fe-13Cr-5Al-2Mo-1ZrC合金的硬度最高，达到306.3 HV，分别比Fe-13Cr-5Al高12.8%和Fe-13Cr-5Al-1ZrC合金高3.7%。此外，Fe-13Cr-5Al-2Mo-1ZrC 样品在 1000°C 退火 20 小时后仍能保持较高的强度和良好的延展性，这表明它们具有优异的热稳定性。Fe-13Cr-5Al-2Mo-1ZrC合金优异的机械性能和热稳定性不仅得益于纳米级ZrC颗粒的分散强化、Mo元素的固溶强化，还得益于Mo和ZrC添加的协同效应所促进的晶粒细化结构。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文去求助

来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.