Non-linear damping of sodium fast reactor fuel pins: Experimental analysis and numerical modelisation

Catterou, Thomas; Blanc, Victor; Guillaume,; Bourgeois, Stéphane; Cochelin, Bruno

doi:10.1016/j.nucengdes.2020.110643

Cited by 3 publications

(1 citation statement)

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“…Scientific literature in the nuclear context has mainly focused on the fretting phenomenon which occurs at the interface between fuel rods and spacer grids as a consequence of FIV. Few researches have been carried out on the impact of the non linear dissipation mechanisms which take place inside the fuel rod, due to the presence of pellets and the existence of a fabrication gap between pellets and gap (Catterou et al, 2020). When the gap is open and FIV are induced, a relative motion establishes between the cladding and the fuel pellets.…”

Section: State Of the Artmentioning

confidence: 99%

Fuel rod nonlinear vibrations to detect and characterize Pellet-Cladding Interaction

d'Ambrosi

Destouches

Ricciardi

et al. 2021

Nuclear Engineering and Design

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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.

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Section: State Of the Artmentioning

confidence: 99%