Pellet-Cladding Interaction (PCI) in a Light Water Reactor is one of the major concerns to guarantee clad integrity while attempting at increasing the flexibility of PWR nuclear reactor operations to follow power grid demand. In order to forbid operations leading to clad failure, modeling capability to simulate the mechanism has improved through the years. Code development needs detailed and precise experimental data. Those data result from dedicated irradiation programs, named “power ramp tests”, carried out in experimental devices in Material Testing Reactors (e.g. in France ISABELLE in OSIRIS in the past (Alberman et al., 1997), the ADELINE loop in the Jules Horowitz Reactor JHR in the next future (Cheymol et al., 2011)). Those irradiation devices are highly instrumented to collect the most relevant information with the highest possible accuracy. In parallel with information gained thanks to post-irradiation examination programs, research is working on innovative methodologies to detect and characterize PCI kinetics during the tests. In this frame, we investigate the technological feasibility to measure the effects of PCI, on the vibrations of a nuclear fuel rod externally submitted to the turbulent axial flow rate excitation. We designed and realized the out-of-pile IMPIGRITIA set-up to reproduce, in controlled laboratory conditions, the mechanical interaction originating in the nuclear reactor. A single PWR rod test section, reproducing the main relevant geometrical and material characteristics of ADELINE experimental system, is submitted to the hydraulic excitation representative of the real case. The local closure of the gap is obtained by means of a remotely controlled expansion system. Measurements of the transverse displacement of the sample rod are collected by Laser Doppler Vibrometry. In this paper we introduce the design of the mock-up and the associated measurement method, then we present the two experimental phases and their results: the first one in air, to show the feasibility of the measurement in air in controlled conditions; the second one under turbulent flow rate to state on the feasibility of the passive detection. At the end, conclusions and perspectives for the work are discussed.

轻水反应堆中的颗粒-包层相互作用（PCI）是在确保增加包层完整性同时试图提高压水堆核反应堆运行的灵活性以适应电网需求的主要考虑之一。为了防止操作导致包层故障，多年来模拟机构的建模能力得到了提高。代码开发需要详细而精确的实验数据。这些数据来自专用辐射程序（称为“功率斜坡测试”）的结果，该程序在材料测试反应堆（例如，法国OSIRIS的ISABELLE（过去在法国，Alberman等人，1997年）），Jules Horowitz中的ADELINE回路中进行。未来的反应堆JHR（Cheymol等，2011）。这些辐照设备具有高度的仪器性，可以以最高的准确性收集最相关的信息。除了通过辐照后检查程序获得的信息外，研究还在研究创新的方法，以检测和表征测试过程中的PCI动力学。在此框架中，我们研究了在外部受湍流轴向流量激励作用的核燃料棒振动方面测量PCI影响的技术可行性。我们设计并实现了桩外IMPIGRITIA装置，以便在受控的实验室条件下重现源自核反应堆的机械相互作用。单个PWR棒测试部分，可再现ADELINE实验系统的主要相关几何和材料特征，被提交给实际案例的水力激励代表。缝隙的局部封闭是通过远程控制的扩展系统获得的。通过激光多普勒振动法收集样品棒的横向位移的测量值。在本文中，我们介绍了模型的设计和相关的测量方法，然后介绍了两个实验阶段及其结果：第一个实验阶段是在空气中，以显示在受控条件下在空气中进行测量的可行性；第二个阶段是在空气中进行测量。第二个在湍流速率下陈述了被动检测的可行性。最后，讨论了工作的结论和观点。通过激光多普勒振动法收集样品棒的横向位移的测量值。在本文中，我们介绍了模型的设计和相关的测量方法，然后介绍了两个实验阶段及其结果：第一个实验阶段是在空气中，以显示在受控条件下在空气中进行测量的可行性；第二个阶段是在空气中进行测量。第二个在湍流速率下陈述了被动检测的可行性。最后，讨论了工作的结论和观点。通过激光多普勒振动法收集样品棒的横向位移的测量值。在本文中，我们介绍了模型的设计和相关的测量方法，然后介绍了两个实验阶段及其结果：第一个实验阶段是在空气中，以显示在受控条件下在空气中进行测量的可行性；第二个阶段是在空气中进行测量。第二个在湍流速率下陈述了被动检测的可行性。最后，讨论了工作的结论和观点。第二个在湍流速率下陈述了被动检测的可行性。最后，讨论了工作的结论和观点。第二个在湍流速率下陈述了被动检测的可行性。最后，讨论了工作的结论和观点。