高密度U3Si2分散燃料的膨胀行为

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-07-26 DOI:10.1016/j.jnucmat.2025.156061

A. Leenaers , J. Wight , S. Van den Berghe , X. Iltis , H. Palancher , B. STEPNIK

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引用次数: 0

摘要

在LEU-FOREvER和eu - qualified项目（H2020 Euratom工作计划）的框架内，进行了一项名为高性能研究堆优化硅化物辐照试验（HiPROSIT）的辐照试验，以证明高密度U3Si2燃料系统的堆内行为是可接受的。HiPROSIT试验由4块燃料板组成，这些燃料板在比利时Mol的BR2反应堆的代表性反应堆条件下进行辐照，作为确定燃料用于高功率研究堆（HPRR）的第一步，主要用于低浓铀转换。每个燃料板都设计有不同载荷的U3Si2燃料，分别为4.8、5.3和5.6 gU/cm3和燃料肉厚度。成功辐照后，所有板都达到了局部最大燃耗约80% U235或约4.3E+21裂变/cm3。该燃料的稳定性和可预测性在无损和微观结构检测中得到了证明。此外，还发现制备的孔隙度可以适应燃料的初始膨胀，从而限制了板的膨胀。

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Swelling behavior of high density U3Si2 dispersion fuel

Within the framework of the LEU-FOREvER and EU-QUALIFY projects (H2020 Euratom work program), an irradiation test called High Performance research Reactors Optimized Silicide Irradiation Test (HiPROSIT) has been performed to demonstrate the acceptable in pile behavior of the high density U₃Si₂ fuel system. The HiPROSIT test consists of four (4) fuel plates which were irradiated at the BR2 reactor in Mol, Belgium in representative reactor conditions as a first step towards qualification of the fuel for use in high power research reactors (HPRR), primarily aimed at LEU conversions. Each of the fuel plates was designed to have U₃Si₂ fuel with various loadings at 4.8, 5.3, and 5.6 gU/cm³ and fuel meat thicknesses. After successful irradiation, all plates have achieved a local maximum burnup of ∼80 % U²³⁵ or ∼4.3E+21 fission/cm³. A stable and predictable behavior of the fuel is evidenced in the nondestructive and microstructural examinations. Furthermore, it was found that the as-fabricated porosity accommodates the initial swelling of the fuel, which limits the swelling of the plate.

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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.