Low-temperature sintering of (U,Pu)O2 MOX in mild oxidative conditions

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-04-01 DOI:10.1016/j.jnucmat.2025.155800
Jacobus Boshoven , Jean-François Vigier , Philipp Pöml , Abibatou Ndiaye , Bertrand Morel , Rudy J.M. Konings , Karin Popa , Marco Cologna
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Abstract

We compare typical reductive sintering conditions for U, Pu mixed oxides (4 h at 1700°C in Ar/6% H2 + 1200 ppm H2O) with lower temperature and mildly oxidative conditions (2 h at 1200°C in CO/CO2 = 1/9) and report on the resulting microstructures and homogeneity. We show that lower temperature and mildly oxidative conditions, without cover gas change, can give close-to stoichiometric, crack-free MOX pellets with a relative density of ∼ 95%, and we propose ways to improve the homogenisations of PuO2 and UO2 and increase the grain size.
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在温和氧化条件下低温烧结(U,Pu)O2 MOX
我们比较了U, Pu混合氧化物的典型还原烧结条件(在Ar/6% H2 + 1200 ppm H2O中1700°C下烧结4小时)和较低温度和轻度氧化条件(在CO/CO2 = 1/9中1200°C烧结2小时),并报告了所得的微观结构和均匀性。我们发现,在没有覆盖气体变化的情况下,较低的温度和轻度氧化条件可以得到接近化学计量的、相对密度为95%的无裂纹MOX颗粒,我们提出了改善PuO2和UO2均质化和增加晶粒尺寸的方法。
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来源期刊
Journal of Nuclear Materials
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.
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