Microstructurally validated stable and predictable swelling in low-enriched uranium monolithic U-10Mo fuel mini-plates

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-03-18 DOI:10.1016/j.jnucmat.2025.155746

William A. Hanson, Daniele Salvato, Adam B. Robinson, Nancy J. Lybeck, Jan-Fong Jue, Tammy L. Trowbridge, Jatuporn Burns, Fidelma G. Di Lemma, Charlyne A. Smith, Margaret A. Marshall, Dennis D. Keiser Jr., Jeffrey J. Giglio, James I. Cole

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Abstract

Qualification of the low-enriched uranium (LEU) monolithic U-10 wt%Mo (U-10Mo) plate-type fuel system requires a demonstration of a stable and predictable fuel swelling behavior over the anticipated operating conditions of the United States high-performance research reactors (USHPRRs) selected for conversion to LEU operation. This will allow each reactor to develop appropriate safety margins that will retain fuel element lifetime coolability. Additionally, the fuel system must maintain performance attributes when fabricated at a commercial scale. The Mini-plate 1 experiment represents the first irradiation test of commercially fabricated miniaturized monolithic LEU U-10Mo fuel plates. The swelling behavior within this experiment was compared against that of historical fuel developmental tests to reveal that the commercially fabricated fuel performed within the current recommended U-10Mo swelling model's predictions. Additionally, the fuel microstructural evolution was evaluated to link initial conditions to subtle variations detected in the swelling response, providing validation and confidence that the fuel system is robust.

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微观结构验证了低浓缩铀整体U-10Mo燃料微型板的稳定和可预测膨胀

低浓铀（LEU）整体u - 10wt %Mo （U-10Mo）板型燃料系统的鉴定要求在美国高性能研究堆（USHPRRs）选择转换为低浓铀运行的预期运行条件下，展示稳定和可预测的燃料膨胀行为。这将允许每个反应堆发展适当的安全余量，以保持燃料元件的寿命冷却性。此外，燃料系统在商业规模制造时必须保持性能属性。Mini-plate 1试验是首次商业化制造的小型化单片低浓铀U-10Mo燃料板辐照试验。将该实验中的膨胀行为与历史上的燃料开发测试进行了比较，结果表明，商业制造的燃料在当前推荐的U-10Mo膨胀模型预测范围内运行。此外，对燃料微观结构演变进行了评估，将初始条件与膨胀响应中检测到的细微变化联系起来，从而验证并确信燃料系统是稳健的。

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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.