整体 LOCA 实验研究高燃耗核燃料的 FFRD 行为

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2024-10-19 DOI:10.1016/j.nucengdes.2024.113633

Hyunwoo Yook, Sunghoon Joung, Chansoo Lee, Youho Lee

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引用次数: 0

摘要

本文介绍了首尔国立大学建立的整体冷却剂损失（LOCA）设施（i-LOCA）。该设施旨在研究轻水反应堆在 LOCA 期间的整体燃料行为，包括包壳氧化、气球和爆裂、回流淬火、二次水化和燃料芯块分散等方面。整体 LOCA 实验使用了三种类型的代用 ZrO2 燃料芯块，代表了不同的燃烧段：无燃料碎片的圆柱形燃料芯块（55 GWd/MTU）、模拟 ∼ 68 GWd/MTU 的不同大小的混合碎片（D = 0.3、0.5、1.0、2.0、3.0 和 5.0 毫米，质量分数相同），以及模拟超高燃烧率燃料的单个小粉末碎片（D = 0.5 毫米，∼94 GWd/MTU）。采用了 Zr-Nb-Sn、Zr-1.1Nb 和 Cr 涂层（15 μm，电弧离子镀）Zr-1.1Nb ATF 包层，棒内部压力范围为 1 MPa 至 7 MPa。由于方位角和轴向温度分布的影响，平均直径较小的代用颗粒的爆裂尺寸和箍应变较大。燃料扩散受棒内压、爆裂尺寸和弹丸碎片尺寸的影响。燃料爆裂时，只有小于爆裂孔宽度的颗粒碎片才会发生扩散，而较大的碎片会阻碍较小碎片的扩散。与混合粉末相比，单个粉末的平均分散分数迅速上升，这表明燃料分散的临界燃烧度在 69-94 GWd/MTU 之间。包层内部氧化长度受爆孔尺寸和剩余燃料颗粒的影响。内氧化的结果证实了美国核管制委员会关于内壁氧化长度假设的正确性。使用电弧离子镀方法生产的 15 μm 铬涂层包壳管与未涂层的参考包壳相比，在爆裂几何形状、燃料分散、内壁氧化和二次水化方面没有明显差异。

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Integral LOCA experiments to study FFRD behavior of high burnup nuclear fuels

This paper introduces the Integral Loss Of Coolant (LOCA) facility (i-LOCA) established at Seoul National University. The facility was designed to investigate the integral fuel behavior of Light Water Reactors during LOCA, encompassing aspects such as cladding oxidation, ballooning and burst, reflood quenching, secondary hydriding, and fuel pellet dispersal. Integral LOCA experiments were carried out using three types of surrogate ZrO₂ pellets, representing various segment burnups: cylindrical pellets with no fuel fragmentation (<55 GWd/MTU), mixed fragments of different sizes simulating ∼68 GWd/MTU (D = 0.3, 0.5, 1.0, 2.0, 3.0, and 5.0 mm with the same mass fraction), and small single powdered fragments simulating ultra-high burnup fuel (D = 0.5 mm, ∼94 GWd/MTU). Zr-Nb-Sn, Zr-1.1Nb, and Cr-coated (15 μm, Arc Ion Plating) Zr-1.1Nb ATF cladding were employed, with rod internal pressures ranging from 1 MPa to 7 MPa. The burst size and hoop strain exhibited significant variations depending on the type of surrogate pellets used, with larger burst sizes and hoop strains observed for smaller average diameters of surrogate pellets due to the effect of azimuthal and axial temperature distribution. Fuel dispersal was influenced by rod internal pressure, burst size, and the size of pellet fragments. Only pellet fragments smaller than the burst hole width underwent dispersal upon fuel burst, while larger fragments blocked the dispersal of smaller fragments. The rapidly escalating average dispersal fraction of single powder compared to mixed powder indicated a threshold burnup for fuel dispersal between 69–94 GWd/MTU. Cladding inner oxidation length was influenced by burst hole size and remaining fuel pellets. The results of inner oxidation confirmed the validity of the U.S. NRC’s assumption regarding the length of inner wall oxidation. The tested 15 μm Cr-coated cladding tubes, produced using the arc ion plating method, exhibited no significant differences in burst geometry, fuel dispersal, inner oxidation, and secondary hydriding when compared to the uncoated reference cladding.

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来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.