2021
DOI: 10.1007/978-3-030-65820-5_17
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Rod-Bundle Thermalhydraulics Mixing Phenomena: 3D Analysis with Cathare-3 of ROSA-2/LSTF Experiment

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Cited by 3 publications
(4 citation statements)
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“…In this summary, we investigate numerically and experimentally the influence of upstream and downstream pressure losses on the stability boundaries. A dedicated platform called EXOCET 1 has been built in CEA Cadarache (France) to study their influence and a 1D numerical model of the facility was developed with the thermal-hydraulic code CATHARE [13]. We compare and validate our data with results from [12], as the geometrical data is close to ours, and investigate the effects of pressure losses on the stability diagram with experimental results from the EXOCET facility.…”
Section: Introductionmentioning
confidence: 86%
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“…In this summary, we investigate numerically and experimentally the influence of upstream and downstream pressure losses on the stability boundaries. A dedicated platform called EXOCET 1 has been built in CEA Cadarache (France) to study their influence and a 1D numerical model of the facility was developed with the thermal-hydraulic code CATHARE [13]. We compare and validate our data with results from [12], as the geometrical data is close to ours, and investigate the effects of pressure losses on the stability diagram with experimental results from the EXOCET facility.…”
Section: Introductionmentioning
confidence: 86%
“…We use the system-scale code CATHARE to solve thermal-hydraulics in the natural circulation loop. The code is a two-fluid six-equation model based on finite differences for scalar fields and finite volumes for vector fields [13]. Moreover, heat conduction in the wall is computed, between the internal and external sides, using three cells.…”
Section: Numerical Modeling With Catharementioning
confidence: 99%
“…The Code for Analysis of Thermal-Hydraulics during an Accident of Reactor and safety Evaluation (CATHARE) is a French thermal-hydraulic modular system code owned and developed since 1979 by CEA, FRAMATOME, Électricité de France (EDF) and the French Radioprotection and Nuclear Safety Institute (IRSN), see Refs. Barre and Bernard, 1990;Emonot et al, 2011;Préa et al, 2020. It is a widely validated code used for nuclear power plant design and safety studies in normal or accidental operation (International Atomic Energy Agency, 2002). Circuit modeling in the CATHARE code is done by assembling hydraulic elements.…”
Section: The Cathare Codementioning
confidence: 99%
“…Experimental data are compared to predictions of the CATHARE thermal hydraulic system code (Bestion, 1990;Emonot et al, 2011;Préa et al, 2020). An objective is to identify and quantify system scale distortions between the two facilities and the reactor and to discuss design choices.…”
Section: Introductionmentioning
confidence: 99%