Stability of self-pressurized, natural circulation, low thermo-dynamic quality, nuclear reactors: The stability performance of the CAREM-25 reactor

Marcel, Christian Pablo; Acuña, F. M.; Zanocco, Pablo; Delmastro, D.F.

doi:10.1016/j.nucengdes.2013.08.057

Cited by 38 publications

(9 citation statements)

References 12 publications

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“…The most prominent feature of 7 CAREM-25 is that the reactor does not have a pressurizer. The balance between the vaporization in the hot leg and the condensation of vapor due to the colder structures in the steam dome achieves self-pressurization in the primary system [15].…”

Section: Different Smr Designsmentioning

confidence: 99%

Nonlinear dynamic modeling and simulation of a passively cooled small modular reactor

Arda

Holbert

2016

Progress in Nuclear Energy

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A nonlinear dynamic model for a passively cooled small modular reactor (SMR) is developed. The nuclear steam supply system (NSSS) model includes representations for reactor core, steam generator, pressurizer, hot leg riser and downcomer. The reactor core is modeled with the combination of: (1) neutronics, using point kinetics equations for reactor power and a single combined neutron group, and (2)

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Section: Different Smr Designsmentioning

confidence: 99%

Nonlinear dynamic modeling and simulation of a passively cooled small modular reactor

Arda

Holbert

2016

Progress in Nuclear Energy

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“…The other way of calculating the coolant mass flow rate is to relateṁ C to the reactor thermal power (Marcel et al, 2013a) …”

Section: Coolant Flow Ratementioning

confidence: 99%

A dynamic model of a passively cooled small modular reactor for controller design purposes

Arda

Holbert

2015

Nuclear Engineering and Design

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“…In the field of nuclear engineering, helical coil designs have also been widely used for steam generators in several types of nuclear power plants such as the Otto Hahn nuclear ship reactor, the Thorium High Temperature Reactor (THTR-300), the Super Phoenix fast reactor, the Advanced Gas-cooled Reactor (AGR), the Fort St. Vrain High Temperature Gas Reactor (HTGR) and the Monju reactor (Matsuura et al, 2007;Santini et al, 2008). In addition, helical coil steam generators are considered for future reactor designs such as International Reactor Innovative and Secure (IRIS), BREST-OD-300, System-integrated Modular Advanced ReacTor (SMART), CAREM-25 and NuScale (Carelli et al, 2004;Dragunov et al, 2012;Kim et al, 2013;Marcel et al, 2013;Ingersoll et al, 2014).…”

Section: Introductionmentioning

confidence: 99%

CFD Simulation of Two-Phase Flows in Helical Coils

et al. 2020

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The behavior of two-phase flow and corresponding flow regimes in helical tubes significantly differ when compared to two-phase flows in straight tubes due to centrifugal and torsion effects. In order to gain physical insight and gather data for validating computational models, a large number of experiments were performed on a helical coil experimental setup operated with a mixture of water and air. The experimental data were used to assess the predictive capabilities of current two-phase Computational Fluid Dynamics (CFD) models based on the Volume of Fluid (VOF) approach. In the present paper, a comparison of the CFD simulation results with the high-resolution experimental data is discussed, with special emphasis on two-phase pressure drops and void fraction distributions. It is shown that the CFD VOF model is able to correctly capture the occurrence of five flow regimes observed in the experiments, namely bubbly flow, plug flow, slug flow, slug-annular flow, and annular flow. However, a good quantitative agreement for pressure drops and void fraction distributions is found in slug flow and slug-annular flow regimes only. The good agreement found only in a limited range of flow regimes demonstrates that there is not a single set of best-practice guidelines for CFD VOF models that can be applied across a wide range of two-phase flow regimes. Also, there is not a single mesh that can be used to simulate all of the flow regimes and a case-specific mesh and time-step convergence study is needed for each individual flow regime. In the current study, optimal mesh size and time step were obtained for a slug flow test case. Hence, good agreement was obtained only for similar flow regimes, leading to significant disagreement with experimental data for test cases with substantially different flow patterns.

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Stability of self-pressurized, natural circulation, low thermo-dynamic quality, nuclear reactors: The stability performance of the CAREM-25 reactor

Cited by 38 publications

References 12 publications

Nonlinear dynamic modeling and simulation of a passively cooled small modular reactor

Nonlinear dynamic modeling and simulation of a passively cooled small modular reactor

A dynamic model of a passively cooled small modular reactor for controller design purposes

CFD Simulation of Two-Phase Flows in Helical Coils

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