Haozheng J. Qu , Maria Higgins , Hamdy Abouelella , Fabiola Cappia , Jatuporn Burns , Lingfeng He , Caleb Massey , Jason Harp , Kevin G. Field , Richard Howard , Rajnikant V. Umretiya , Andrew K. Hoffman , Janelle P. Wharry , Raul B. Rebak
{"title":"轻水堆环境中FeCrAl燃料/包壳的化学相互作用","authors":"Haozheng J. Qu , Maria Higgins , Hamdy Abouelella , Fabiola Cappia , Jatuporn Burns , Lingfeng He , Caleb Massey , Jason Harp , Kevin G. Field , Richard Howard , Rajnikant V. Umretiya , Andrew K. Hoffman , Janelle P. Wharry , Raul B. Rebak","doi":"10.1016/j.jnucmat.2023.154717","DOIUrl":null,"url":null,"abstract":"<div><p><span><span>This article investigates the fuel-cladding chemical interaction (FCCI) behavior of two commercial FeCrAl alloys, APMT composition (Fe-21Cr-5Al-3Mo wt.%) and C35M (Fe-13Cr-5Al-2Mo-0.2Si-0.03Y wt.%), after neutron irradiation. “H-cup” </span>diffusion multiples of FeCrAl alloys and ceramic UO</span><sub>2</sub><span><span><span><span> fuel were irradiated at a temperature of ∼300 °C to a total estimated burnup of 26 GWd/tHM. Post-irradiation Examination results demonstrate the excellent </span>degradation resistance of FeCrAl alloys as accident tolerant fuel (ATF) </span>cladding materials<span><span><span> in light water reactor conditions. The study concludes that there was no irradiation-induced defects observed in either of the two commercial FeCrAl claddings. The formation of </span>amorphous<span> Al/U mixed oxide was observed at the fuel-clad interface, which can serve as a </span></span>tritium </span></span>permeation<span> barrier and protect against potential chemical attack from the fuel. The study attributed the formation of amorphous Al/U mixed oxide to the low temperature and limited time of neutron irradiation. APMT forms more distinct Cr and Cr-Fe intermetallic at the FeCrAl-UO</span></span><sub>2</sub> interface than C35M due to the higher bulk Cr:Al ratio.</p></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"587 ","pages":"Article 154717"},"PeriodicalIF":2.8000,"publicationDate":"2023-09-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"1","resultStr":"{\"title\":\"FeCrAl fuel/clad chemical interaction in light water reactor environments\",\"authors\":\"Haozheng J. Qu , Maria Higgins , Hamdy Abouelella , Fabiola Cappia , Jatuporn Burns , Lingfeng He , Caleb Massey , Jason Harp , Kevin G. Field , Richard Howard , Rajnikant V. Umretiya , Andrew K. Hoffman , Janelle P. Wharry , Raul B. Rebak\",\"doi\":\"10.1016/j.jnucmat.2023.154717\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><p><span><span>This article investigates the fuel-cladding chemical interaction (FCCI) behavior of two commercial FeCrAl alloys, APMT composition (Fe-21Cr-5Al-3Mo wt.%) and C35M (Fe-13Cr-5Al-2Mo-0.2Si-0.03Y wt.%), after neutron irradiation. “H-cup” </span>diffusion multiples of FeCrAl alloys and ceramic UO</span><sub>2</sub><span><span><span><span> fuel were irradiated at a temperature of ∼300 °C to a total estimated burnup of 26 GWd/tHM. Post-irradiation Examination results demonstrate the excellent </span>degradation resistance of FeCrAl alloys as accident tolerant fuel (ATF) </span>cladding materials<span><span><span> in light water reactor conditions. The study concludes that there was no irradiation-induced defects observed in either of the two commercial FeCrAl claddings. The formation of </span>amorphous<span> Al/U mixed oxide was observed at the fuel-clad interface, which can serve as a </span></span>tritium </span></span>permeation<span> barrier and protect against potential chemical attack from the fuel. The study attributed the formation of amorphous Al/U mixed oxide to the low temperature and limited time of neutron irradiation. APMT forms more distinct Cr and Cr-Fe intermetallic at the FeCrAl-UO</span></span><sub>2</sub> interface than C35M due to the higher bulk Cr:Al ratio.</p></div>\",\"PeriodicalId\":373,\"journal\":{\"name\":\"Journal of Nuclear Materials\",\"volume\":\"587 \",\"pages\":\"Article 154717\"},\"PeriodicalIF\":2.8000,\"publicationDate\":\"2023-09-08\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"1\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Journal of Nuclear Materials\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0022311523004841\",\"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}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Materials","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0022311523004841","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}
FeCrAl fuel/clad chemical interaction in light water reactor environments
This article investigates the fuel-cladding chemical interaction (FCCI) behavior of two commercial FeCrAl alloys, APMT composition (Fe-21Cr-5Al-3Mo wt.%) and C35M (Fe-13Cr-5Al-2Mo-0.2Si-0.03Y wt.%), after neutron irradiation. “H-cup” diffusion multiples of FeCrAl alloys and ceramic UO2 fuel were irradiated at a temperature of ∼300 °C to a total estimated burnup of 26 GWd/tHM. Post-irradiation Examination results demonstrate the excellent degradation resistance of FeCrAl alloys as accident tolerant fuel (ATF) cladding materials in light water reactor conditions. The study concludes that there was no irradiation-induced defects observed in either of the two commercial FeCrAl claddings. The formation of amorphous Al/U mixed oxide was observed at the fuel-clad interface, which can serve as a tritium permeation barrier and protect against potential chemical attack from the fuel. The study attributed the formation of amorphous Al/U mixed oxide to the low temperature and limited time of neutron irradiation. APMT forms more distinct Cr and Cr-Fe intermetallic at the FeCrAl-UO2 interface than C35M due to the higher bulk Cr:Al ratio.
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.
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