Experimental qualification of subassembly design for Prototype Fast Breeder Reactor

Prakash, V.; Thirumalai, M.; Anandaraj, M.; Kumar, Pradeep; Ramdasu, D.; Pandey, G.K.; Padmakumar, G.; Anandbabu, C.; Kalyanasundaram, P.

doi:10.1016/j.nucengdes.2011.04.040

Cited by 28 publications

(5 citation statements)

References 5 publications

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“…Hydraulics is designed in order to reproduce the external solicitation in terms of the axial turbulent flow and pressure fluctuation in the flow. We identified a range of representative flow rates, imposing two principles: the conservation of wall pressure fluctuations and the Burgreen principle (Prakash et al, 2011). The conservation of wall pressure fluctuation p rms was imposed according to the definition proposed by Axisa in Axisa (2001) on the basis of the envelop PSD derived from Clinch data (Clinch, 1969) and reported in Eq.…”

Section: The Hydraulic Designmentioning

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: The Hydraulic Designmentioning

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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“…The conservation of wall pressure fluctuation p r.m.s was imposed according to the definition proposed by Axisa in [5] on the basis of the envelop PSD derived from Clinch data [16] and reported in equation (9). The simulation criterion established by Burgreen [17] instead has been recently used by De Paw et al in [11] to study flow induced vibrations in a prototype representative of the MHYRRA system and it is reported in equation (10). c exp = c ρ 0.5 µ −0.33 E −0.33 M 0.165 ρ 0.5 exp µ −0.33 exp E −0.33 exp M 0.165 exp (10) Subscript 'exp' stands for prototype, µ the fluid dynamic viscosity, E elastic modulus and M the mass of the sample rod at operating temperature.…”

Section: B the Representativeness Issuementioning

confidence: 99%

Experimental characterization of PCI impact on vibrating fuel rod under axial turbulent flow representative of JHR irradiation device ADELINE: Set-up conception and measurement method

et al. 2020

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Mechanical loading originating due to Pellet- Cladding Interaction (PCI) in PWR nuclear fuel rod constitutes a first order importance phenomenon when attempting at increasing the flexibility o f n uclear r eactors o peration t o f ollow grid demand. The need to improve the understanding of such complex multi-physics phenomena motivates the realization of particular irradiation sequences carried out in highly instrumented devices located in Material Testing Reactors. Among this kind, ADELINE irradiation device is being developed and will be installed in the future Jules Horowitz Reactor. In the perspective of designing the adapted measurement methodology to detect and characterize PCI phenomenology during irradiation, we present in this paper the experimental bench and its associated measurement program, designed to investigate eventual effects of PCI on the non-linear, flow i nduced v ibrations o fuclear fuel r od. A nalytical and numerical models cannot predictively describe the system due to the complexity of phenomena thus the IMPIGRITIA experimental set-up has been developed to reproduce the mechanical interaction between the pellet and the clad at low pressure, room temperature and out of neutron flux. T he d esigned test bench presents a clamped free single short rod, centred in the test section by mean of four centring elements. Different rod configurations are implemented and localized closure of the gap is remotely realized by means of a dilatation system. Laser Doppler Vibrometry is used to measure the transversal displacement of the sample rod in three different conditions: in air, in stagnant water and under turbulent axial flow r ate. T he experimental program and expected results are presented and discussed

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“…Such flow conditions yield a turbulent regime and can excite flow-induced vibrations (FIV) of the fuel rods and of the entire sub-assembly as a whole. Since we have axial flow and turbulence as the main excitation mechanism we can use the simulation criterion established by Burgreen (Prakash et al, 2011). This criterion allows calculating the required flow speed and temperature of any fluid, e.g.…”

Section: Flow-induced Vibration Correlationmentioning

confidence: 99%

Operational modal analysis of flow-induced vibration of nuclear fuel rods in a turbulent axial flow

Pauw

Weijtjens

Vanlanduit

et al. 2015

Nuclear Engineering and Design

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Experimental qualification of subassembly design for Prototype Fast Breeder Reactor

Cited by 28 publications

References 5 publications

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

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

Experimental characterization of PCI impact on vibrating fuel rod under axial turbulent flow representative of JHR irradiation device ADELINE: Set-up conception and measurement method

Operational modal analysis of flow-induced vibration of nuclear fuel rods in a turbulent axial flow

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