Anna Oberbauer, Christian Schwarz, Bruno Baumeister, Tobias Chemnitz, Christian Reiter, Jingyi Shi, Winfried Petry
{"title":"Al涂层三元UMoX合金的热扩散行为","authors":"Anna Oberbauer, Christian Schwarz, Bruno Baumeister, Tobias Chemnitz, Christian Reiter, Jingyi Shi, Winfried Petry","doi":"10.1016/j.jnucmat.2025.156029","DOIUrl":null,"url":null,"abstract":"<div><div>Uranium-molybdenum (UMo) alloys are characterized by 7–10 wt.% Mo content and offer assurance in achieving high densities of U assemblies in fuel compositions, making them a compelling option for research reactors in the quest for high neutron fluxes. However, the use of these materials in fuel plates faces numerous challenges, mostly reflected in the formation of an amorphous interdiffusion layer (IDL) with poor thermal conductivity between the UMo kernel and the Al matrix or cladding. In addition, swelling of the fuel plate and accumulation of gaseous fission products can be observed. These effects can be suppressed by introducing an interdiffusion barrier layer (IDB) between the fuel and the Al matrix/cladding or using ternary alloys (UMoX) instead of binary UMo. This experiment focuses on the second approach, the investigation of ternary UMoX alloys. Zr, Pt, Nb, and Ti are selected as the third candidate element (X) because of their relevant material properties. The experimental work involved the production of UMoX alloys, with a subset of samples undergoing heat treatment at 1173 K for homogenization. All samples were coated with Al using physical vapor deposition (PVD) to mimic the Al matrix and/or cladding in fuel plates. Both the ternary alloys and binary UMo reference samples were annealed to simulate the diffusion processes expected during in-pile operation and to study γ-phase stability. The results revealed that UMoTi and UMoZr are not suitable because of irregular interdiffusion. UMoPt formed a relatively thin and regular IDL compared to that of pure UMo. UMoNb did not show interdiffusion and was chemically stable under long heat treatment. In conclusion, UMoNb and UMoPt are promising candidates for high-density fuels, offering a simpler alternative to UMo fuels, as they do not require an additional IDB layer.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"616 ","pages":"Article 156029"},"PeriodicalIF":2.8000,"publicationDate":"2025-07-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Thermal diffusion behavior of ternary UMoX alloys with Al coating\",\"authors\":\"Anna Oberbauer, Christian Schwarz, Bruno Baumeister, Tobias Chemnitz, Christian Reiter, Jingyi Shi, Winfried Petry\",\"doi\":\"10.1016/j.jnucmat.2025.156029\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Uranium-molybdenum (UMo) alloys are characterized by 7–10 wt.% Mo content and offer assurance in achieving high densities of U assemblies in fuel compositions, making them a compelling option for research reactors in the quest for high neutron fluxes. However, the use of these materials in fuel plates faces numerous challenges, mostly reflected in the formation of an amorphous interdiffusion layer (IDL) with poor thermal conductivity between the UMo kernel and the Al matrix or cladding. In addition, swelling of the fuel plate and accumulation of gaseous fission products can be observed. These effects can be suppressed by introducing an interdiffusion barrier layer (IDB) between the fuel and the Al matrix/cladding or using ternary alloys (UMoX) instead of binary UMo. This experiment focuses on the second approach, the investigation of ternary UMoX alloys. Zr, Pt, Nb, and Ti are selected as the third candidate element (X) because of their relevant material properties. The experimental work involved the production of UMoX alloys, with a subset of samples undergoing heat treatment at 1173 K for homogenization. All samples were coated with Al using physical vapor deposition (PVD) to mimic the Al matrix and/or cladding in fuel plates. Both the ternary alloys and binary UMo reference samples were annealed to simulate the diffusion processes expected during in-pile operation and to study γ-phase stability. The results revealed that UMoTi and UMoZr are not suitable because of irregular interdiffusion. UMoPt formed a relatively thin and regular IDL compared to that of pure UMo. UMoNb did not show interdiffusion and was chemically stable under long heat treatment. In conclusion, UMoNb and UMoPt are promising candidates for high-density fuels, offering a simpler alternative to UMo fuels, as they do not require an additional IDB layer.</div></div>\",\"PeriodicalId\":373,\"journal\":{\"name\":\"Journal of Nuclear Materials\",\"volume\":\"616 \",\"pages\":\"Article 156029\"},\"PeriodicalIF\":2.8000,\"publicationDate\":\"2025-07-14\",\"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/S0022311525004234\",\"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/S0022311525004234","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}
Thermal diffusion behavior of ternary UMoX alloys with Al coating
Uranium-molybdenum (UMo) alloys are characterized by 7–10 wt.% Mo content and offer assurance in achieving high densities of U assemblies in fuel compositions, making them a compelling option for research reactors in the quest for high neutron fluxes. However, the use of these materials in fuel plates faces numerous challenges, mostly reflected in the formation of an amorphous interdiffusion layer (IDL) with poor thermal conductivity between the UMo kernel and the Al matrix or cladding. In addition, swelling of the fuel plate and accumulation of gaseous fission products can be observed. These effects can be suppressed by introducing an interdiffusion barrier layer (IDB) between the fuel and the Al matrix/cladding or using ternary alloys (UMoX) instead of binary UMo. This experiment focuses on the second approach, the investigation of ternary UMoX alloys. Zr, Pt, Nb, and Ti are selected as the third candidate element (X) because of their relevant material properties. The experimental work involved the production of UMoX alloys, with a subset of samples undergoing heat treatment at 1173 K for homogenization. All samples were coated with Al using physical vapor deposition (PVD) to mimic the Al matrix and/or cladding in fuel plates. Both the ternary alloys and binary UMo reference samples were annealed to simulate the diffusion processes expected during in-pile operation and to study γ-phase stability. The results revealed that UMoTi and UMoZr are not suitable because of irregular interdiffusion. UMoPt formed a relatively thin and regular IDL compared to that of pure UMo. UMoNb did not show interdiffusion and was chemically stable under long heat treatment. In conclusion, UMoNb and UMoPt are promising candidates for high-density fuels, offering a simpler alternative to UMo fuels, as they do not require an additional IDB layer.
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.