The SPES3 Experimental Facility Design for the IRIS Reactor Simulation

Carelli, Mario D.; Conway, L.; Dzodzo, Milorad B.; Maioli, Andrea; Oriani, L.; Storrick, Gary D.; Petrović, Bojan; Achilli, Andrea; Cattadori, G.; Congiu, C.; Ferri, R.; Ricotti, Marco Enrico; Papini, Davide; Bianchi, F.; Méloni, P.; Monti, Stefano; Berra, F.; Grgić, Davor; Yoder, G.L.; Alemberti, A.

doi:10.1155/2009/579430

Cited by 18 publications

(9 citation statements)

References 4 publications

(4 reference statements)

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“…Potential applications of the proposed anomaly detection method include real-time detection of component-level anomalies in nuclear power plants with low false alarm and missed detection rates. While the training stage could be accomplished in a nuclear power plant simulator with high fidelity (e.g., scaled experimental reactor [34] or computer simulator [35]), the testing stage should be ideally performed in real time in an operating nuclear power plant. However, based on the simulation results only, it is found that the plant perturbation needed to execute the proposed anomaly detection method require small induced changes in the turbine load (e.g., less than 2% nominal load) over a short period, which does not have any significant adverse effects on stability and performance of the plant operation.…”

Section: Summary Conclusion and Future Workmentioning

confidence: 99%

Anomaly Detection in Nuclear Power Plants via Symbolic Dynamic Filtering

Jin

Guo

Sarkar

et al. 2011

IEEE Trans. Nucl. Sci.

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Tools of sensor-data-driven anomaly detection facilitate condition monitoring of dynamical systems especially if the physics-based models are either inadequate or unavailable. Along this line, symbolic dynamic filtering (SDF) has been reported in literature as a real-time data-driven tool of feature extraction for pattern identification from sensor time series. However, an inherent difficulty for a data-driven tool is that the quality of detection may drastically suffer in the event of sensor degradation. This paper proposes an anomaly detection algorithm for condition monitoring of nuclear power plants, where symbolic feature extraction and the associated pattern classification are optimized by appropriate partitioning of (possibly noise-contaminated) sensor time series. In this process, the system anomaly signatures are identified by masking the sensor degradation signatures. The proposed anomaly detection methodology is validated on the International Reactor Innovative & Secure (IRIS) simulator of nuclear power plants, and its performance is evaluated by comparison with that of principal component analysis (PCA).

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Section: Summary Conclusion and Future Workmentioning

confidence: 99%

Anomaly Detection in Nuclear Power Plants via Symbolic Dynamic Filtering

Jin

Guo

Sarkar

et al. 2011

IEEE Trans. Nucl. Sci.

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“…The conceptual design and features of SPES3 IET facility are presented in Ref. [8]. The basic scaling criteria for designing SPES3 as a model for the IRIS prototype were:…”

Section: Introductionmentioning

confidence: 99%

Application of Fractional Scaling Analysis for Development and Design of Integral Effects Test Facility

Dzodzo

Oriolo

Ambrosini

et al. 2019

Journal of Nuclear Engineering and Radiation Science

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The aim of this paper is to present a fractional scaling analysis (FSA) application for a system with interacting components where multiple figures of merits need to be respected during complex transient accident scenario with several consecutive time sequences. This paper presents FSA application to the International Reactor Innovative and Secure (IRIS) reactor and Simulatore Pressurizzato per Esperienze di Sicurezza 3 (SPES3) integral effects test (IET) facility. The FSA was applied for the small break loss of coolant accident (SBLOCA) on the direct vessel injection (DVI) line as the most challenging transient scenario. The FSA methodologies were applied for two figures of merits: (1) reactor and containment vessels pressure responses, and (2) reactor vessel water collapsed level response. The space decomposition was performed first. The reactor vessel and containment vessel were divided in components so that important phenomena and their consequences can be evaluated in each of them. After that, the time decomposition in consecutive time sequences was performed for the considered transient (DVI SBLOCA) based on the starts, or ends, of the defining events. The configuration of the system in each time sequence might be different and dependent on the control system actions connecting, or disconnecting, various components of the system due to the valves openings, or closings. This way, the important phenomena and their consequences can be evaluated for each component and time sequence. Also, this paper presents and discusses options for deriving nondimensional groups and calculation of distortions between prototype and model responses for complex transients containing multiple consecutive time sequences. The input data for scaling analysis are based on the results of RELAP/GOTHIC analysis performed for IRIS and RELAP analysis performed for SPES3. The scaling analysis was applied iteratively several times for different IRIS and SPES3 configurations. Based on the intermediate results, some components in the IRIS and SPES3 were redesigned so that the distortions between IRIS and SPES3 responses are decreased.

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“…The design of new nuclear reactors requires carrying out integral and separate effect tests on simulation facilities, as well as performing safety systems verification and safety code validation. Within the framework of an Italian R&D program on nuclear fission, managed by ENEA and supported by the Ministry of Economic Development, the SPES3 (pressurized simulator for safety experiments) experimental facility, described by Carelli et al [1], able to simulate the innovative small and medium size (PWR pressurized water reactor) nuclear reactors, is being built and will be operated at the SIET Company laboratories in Piacenza, Italy. In such facility, some design and beyond design basis accidents, like loss of coolant accidents (LOCAs), with and without the emergency heat removal systems, will be simulated [2].…”

Section: Introductionmentioning

confidence: 99%

Electrical Capacitance Probe Characterization in Vertical Annular Two-Phase Flow

Monni¹,

Salve²,

Panella

et al. 2013

Science and Technology of Nuclear Installations

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The paper presents the experimental analysis and the characterization of an electrical capacitance probe (ECP) that has been developed at the SIET Italian Company, for the measurement of two-phase flow parameters during the experimental simulation of nuclear accidents, as LOCA. The ECP is used to investigate a vertical air/water flow, characterized by void fraction higher than 95%, with mass flow rates ranging from 0.094 to 0.15 kg/s for air and from 0.002 to 0.021 kg/s for water, corresponding to an annular flow pattern. From the ECP signals, the electrode shape functions (i.e., the signals as a function of electrode distances) in single- and two-phase flows are obtained. The dependence of the signal on the void fraction is derived and the liquid film thickness and the phase’s velocity are evaluated by means of rather simple models. The experimental analysis allows one to characterize the ECP, showing the advantages and the drawbacks of this technique for the two-phase flow characterization at high void fraction.

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The SPES3 Experimental Facility Design for the IRIS Reactor Simulation

Cited by 18 publications

References 4 publications

Anomaly Detection in Nuclear Power Plants via Symbolic Dynamic Filtering

Anomaly Detection in Nuclear Power Plants via Symbolic Dynamic Filtering

Application of Fractional Scaling Analysis for Development and Design of Integral Effects Test Facility

Electrical Capacitance Probe Characterization in Vertical Annular Two-Phase Flow

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