PANDA: A Multipurpose Integral Test Facility for LWR Safety Investigations

Paladino, Domenico; Dreier, J.

doi:10.1155/2012/239319

Cited by 37 publications

(6 citation statements)

References 11 publications

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“…The goals of this work are (i) to analyze and interpret the experimental results from the pool test with sparger performed in the PPOOLEX (LUT, Finland) [30] and PANDA (PSI, Switzerland) [31] facilities and (ii) to discuss possible modelling approaches for the observed phenomena. The tests were designed to investigate the large-scale temperature and velocity fields induced by the steam injection, which can be used to develop and validate EHS/EMS modelling approaches implemented in CFD.…”

Section: Introductionmentioning

confidence: 99%

Pool stratification and mixing induced by steam injection through spargers: analysis of the PPOOLEX and PANDA experiments

Gallego-Marcos

Kudinov

Villanueva

et al. 2018

Nuclear Engineering and Design

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Spargers are mutli-hole injection pipes used in Boiling Water Reactors (BWR) and Advanced Pressurized (AP) reactors to condense steam in large water pools. A steam injection induces heat, momentum and mass sources that depend on the steam injection conditions and can result in thermal stratification or mixing of the pool. Thermal stratification reduces the steam condensation capacity of the pool, increases the pool surface temperature and thus the containment pressure. Development of models with predictive capabilities requires the understanding of basic phenomena that govern the behavior of the complex multi-scale system. The goals of this work are (i) to analyze and interpret the experiments on steam injection into a pool through spargers performed in the large-scale facilities of PPOOLEX and PANDA, and (ii) to discuss possible modelling approaches for the observed phenomena. A scaling approach was developed to address the most important physical phenomena and regimes relevant to prototypic plant conditions. The focus of the tests was on the low steam mass flux and oscillatory bubble condensation regimes, which are expected during a long-term steam injection transient, e.g. in the case of a Station Black Out (SBO). Exploratory tests were also done for chugging and stable jet conditions. The results showed a similar behavior in PPOOLEX and PANDA in terms of jet induced by steam condensation, pool stratification, and development of hot layer and erosion of the cold one. A correlation using the Richardson number is proposed to model the erosion rate of the cold layer as a function of the pool dimensions and steam injection conditions.

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Section: Introductionmentioning

confidence: 99%

Pool stratification and mixing induced by steam injection through spargers: analysis of the PPOOLEX and PANDA experiments

Gallego-Marcos

Kudinov

Villanueva

et al. 2018

Nuclear Engineering and Design

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“…Second, X-ray computed tomography (CT) is applied to obtain contactless cross-sectional images of the flow morphology inside the condenser tube at five various cross sections along the tube without interfering the flow stream. The PANDA multi-purpose facility was set up at Paul Scherrer Institute (PSI) as a scaled thermal-hydraulic test facility for investigating passive decay heat removal systems for the new generation of light water reactors (LWR) [112]. As shown in Figure 15, LWR containment volumes are simulated by six cylindrical pressure vessels representing the reactor, RPV, drywell, the suppression chamber (SC) and the gravity driven cooling system (GDCS) pool.…”

Section: Experimental Test Facilitiesmentioning

confidence: 99%

Modelling of Passive Heat Removal Systems: A Review with Reference to the Framatome KERENA BWR Reactor: Part I

et al. 2019

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Passive safety systems are an important feature of currently designed and constructed nuclear power plants. They operate independent of external power supply and manual interventions and are solely driven by thermal gradients and gravitational force. This brings up new needs for performance and reliably assessment. This paper provides a review on fundamental approaches to model and analyze the performance of passive heat removal systems exemplified for the passive heat removal chain of the KERENA boiling water reactor concept developed by Framatome. We discuss modelling concepts for one-dimensional system codes such as ATHLET, RELAP and TRACE and furthermore for computational fluid dynamics codes. Part I deals with numerical and experimental methods for modelling of condensation inside the emergency condensers and on the containment cooling condenser while part II deals with boiling and two-phase flow instabilities.

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“…The containment compartments and the reactor pressure vessel (RPV) are simulated in the PANDA facility by six cylindrical pressure vessels, Figure 1. For a comparison of the main components of a european simplified boiling water reactor (ESBWR) and the PANDA facility see [5]. The overall height of the facility is 25 m, the total volume of the vessels is about 530 m 3 , and the maximum operating conditions are 10 bar at 200 • C. The reactor pressure vessel (RPV) is electrically heated with a maximum power of 1.5 MW.…”

Section: Facility and Instrumentationmentioning

confidence: 99%

“…These tests have been and will be embedded in international projects, most of which under the auspices of the EU and OECD and with the support of a large number of organizations (regulatory bodies, technical support organizations, national laboratories, electrical utilities, and industries) worldwide. For an overview of these projects, see [5].…”

Section: Introductionmentioning

confidence: 99%

Large-Scale Containment Cooler Performance Experiments under Accident Conditions

Kapulla

Mignot

Paladino

2012

Science and Technology of Nuclear Installations

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Computational Fluid Dynamics codes are increasingly used to simulate containment conditions after various transient accident scenarios. This paper presents validation experiments, conducted in the frame of the OECD/SETH-2 project. These experiments address the combined effects of mass sources and heat sinks related to gas mixing and hydrogen transport within containment compartments. A wall jet interacts with an operating containment cooler located in the middle (M-configuration) and the top (T-configuration) of the containment vessel. The experiments are characterized by a 3-phase injection scenario. In Phase I, pure steam is injected, while in Phase II, a helium-steam mixture is injected. Finally, in Phase III, pure steam is injected again. Results for the M-configuration show helium stratification build up during Phase II. During Phase III, a positively buoyant plume emerging from the cooler housing becomes negatively buoyant once it reaches the helium-steam layer and continuously erodes the layer. For the M-configuration, a strong degradation of the cooler performance was observed during the injection of the helium/steam mixture (Phase II). For the T-configuration, we observe a mainly downwards acting cooler resulting in a combination of forced and natural convection flow patterns. The cooler performance degradation was much weaker compared with the M-configuration and a good mixing was ensured by the operation of the cooler.

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PANDA: A Multipurpose Integral Test Facility for LWR Safety Investigations

Cited by 37 publications

References 11 publications

Pool stratification and mixing induced by steam injection through spargers: analysis of the PPOOLEX and PANDA experiments

Pool stratification and mixing induced by steam injection through spargers: analysis of the PPOOLEX and PANDA experiments

Modelling of Passive Heat Removal Systems: A Review with Reference to the Framatome KERENA BWR Reactor: Part I

Large-Scale Containment Cooler Performance Experiments under Accident Conditions

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