高燃耗U-19Pu-10Zr的辐照后比较研究:根据历史和模型燃料性能评估稳态辐照行为

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Allison Probert , Alexander Swearingen , Jason Schulthess , Luca Capriotti , Colby Jensen , Assel Aitkaliyeva
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引用次数: 0

摘要

下一代钠冷快堆的发展需要对金属燃料进行全面的研究,以最大限度地提高经济性能,同时确保安全运行。在这项研究中,我们研究了两种高燃耗U-19Pu-10Zr燃料销DP-36和DP-40的稳态辐照行为,为计划的安全测试做准备。辐照后检查(PIE)用于量化燃料柱伸长率、燃料柱顶部低密度区域、销变形、裂变产物分布、分式裂变气体释放、微观结构演变和燃料成分再分布。对现有的EBR-II辐照U-19Pu-10Zr燃料销的PIE数据进行基准测试,发现燃料柱伸长率和包层直径应变的模式一致。然而,两种引脚都表现出较长的低密度结构,并且DP-36的破坏性检查显示,与先前报道的三元燃料引脚数据相比,其成分再分布模式更复杂。两针的稳态辐照也用BISON模型模拟。PIE结果与模型预测的比较表明,裂变气体释放的分数总体上是一致的,但由于气体和固体膨胀模型,轴向和径向膨胀的估计一致过高。这些发现强调了测试前对测试和兄弟引脚进行测试表征的重要性,以便在瞬态测试之前准确捕获稳态燃料行为,从而为测试后比较建立基线。此外,这些分析确定了关键的数据缺口,值得进一步研究,以提高对燃料膨胀的理解和预测,从而增强模型和实验工作之间的协同作用,以支持事故测试。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Comparative post-irradiation examination of high burnup U-19Pu-10Zr: Assessing steady-state irradiation behavior against historical and modeled fuel performance
The development of next-generation sodium-cooled fast reactors necessitates comprehensive research on metallic fuels to maximize economic performance while ensuring safe operation. In this study, we investigated the steady-state irradiation behavior of two high burnup U-19Pu-10Zr fuel pins, DP-36 and DP-40, in preparation for planned safety testing. Post-irradiation examination (PIE) was performed to quantify fuel column elongation, regions of low-density at the top of the fuel column, pin deformation, fission product distribution, fractional fission gas release, microstructural evolution, and fuel constituent redistribution. Benchmarking against existing PIE data from U-19Pu-10Zr fuel pins irradiated in EBR-II revealed consistent patterns in fuel column elongation and cladding diametral strain. However, both pins exhibited longer low-density structures, and destructive examination of DP-36 revealed more complex constituent redistribution patterns compared to previously reported data for ternary fuel pins. The steady-state irradiation of both pins was also modeled using BISON. Comparisons of PIE results with modeled predictions showed overall agreement in fractional fission gas release but consistent overestimation of axial and radial swelling due to gaseous and solid swelling models. These findings underscore the critical importance of pre-test characterization on test and sibling pins to accurately capture steady-state fuel behavior ahead of transient testing, thus establishing a baseline for post-test comparison. Additionally, these analyses identified key data gaps that warrant further investigation to improve the understanding and prediction of fuel swelling, thereby enhancing the synergy between modeling and experimental efforts in supporting accident testing.
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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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