High dose ion irradiation response of large strain extrusion machined ultrafine grain HT-9 steel

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-02-12 DOI:10.1016/j.jnucmat.2025.155697

Hyosim Kim , Jonathan G. Gigax , Matthew R. Chancey , Mert. Efe , Jon K.S. Baldwin , Yongqiang Wang , Stuart A. Maloy , Osman El Atwani

{"title":"High dose ion irradiation response of large strain extrusion machined ultrafine grain HT-9 steel","authors":"Hyosim Kim , Jonathan G. Gigax , Matthew R. Chancey , Mert. Efe , Jon K.S. Baldwin , Yongqiang Wang , Stuart A. Maloy , Osman El Atwani","doi":"10.1016/j.jnucmat.2025.155697","DOIUrl":null,"url":null,"abstract":"<div><div>Grain size refinement is one of the many methods to improve radiation resistance of steels. In this study, ultrafine grain HT-9 steel (grain size < ∼270 nm), a potential candidate material for future nuclear fission reactor designs, was manufactured by large strain extrusion machining (LSEM). Radiation resistance of this ultrafine grain HT-9 steel was tested for the first time at high dose using a 3.5 MeV Fe ion beam up to 500 peak displacements-per-atom (dpa) at 450 °C. Results were characterized using a transmission electron microscopy (TEM). Although previous study on the pristine LSEM HT-9 showed that ultrafine grains are thermally stable up to 700 °C, irradiation induced grain growth was observed after 200 peak dpa. Grain boundary carbides were stable after 200 peak dpa with notable dissolution into the matrix in between 200 and 300 peak dpa. The grain size remained in the ultrafine regime (<350 nm) even after the 500 peak dpa irradiation indicating superior grain stability. LSEM HT-9 showed only 0.14 % swelling after 300 peak dpa (181 average local dpa) but showed a steeper rise after 400 peak dpa (242 average local dpa) reaching 1.57 %. However, the rate of swelling between 300 and 400 peak dpa and 400–500 peak dpa decreased significantly from 0.014 to 0.003 %/dpa. The LSEM HT-9 void swelling trend was compared with the void swelling data of other ion and neutron irradiated HT-9 alloys, and the result was discussed with respect to the irradiation induced grain growth, chemical segregation at the grain boundary and precipitation.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"607 ","pages":"Article 155697"},"PeriodicalIF":2.8000,"publicationDate":"2025-02-12","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/S0022311525000923","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

Grain size refinement is one of the many methods to improve radiation resistance of steels. In this study, ultrafine grain HT-9 steel (grain size < ∼270 nm), a potential candidate material for future nuclear fission reactor designs, was manufactured by large strain extrusion machining (LSEM). Radiation resistance of this ultrafine grain HT-9 steel was tested for the first time at high dose using a 3.5 MeV Fe ion beam up to 500 peak displacements-per-atom (dpa) at 450 °C. Results were characterized using a transmission electron microscopy (TEM). Although previous study on the pristine LSEM HT-9 showed that ultrafine grains are thermally stable up to 700 °C, irradiation induced grain growth was observed after 200 peak dpa. Grain boundary carbides were stable after 200 peak dpa with notable dissolution into the matrix in between 200 and 300 peak dpa. The grain size remained in the ultrafine regime (<350 nm) even after the 500 peak dpa irradiation indicating superior grain stability. LSEM HT-9 showed only 0.14 % swelling after 300 peak dpa (181 average local dpa) but showed a steeper rise after 400 peak dpa (242 average local dpa) reaching 1.57 %. However, the rate of swelling between 300 and 400 peak dpa and 400–500 peak dpa decreased significantly from 0.014 to 0.003 %/dpa. The LSEM HT-9 void swelling trend was compared with the void swelling data of other ion and neutron irradiated HT-9 alloys, and the result was discussed with respect to the irradiation induced grain growth, chemical segregation at the grain boundary and precipitation.

Abstract Image

查看原文本刊更多论文

求助全文

约1分钟内获得全文求助全文

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.