Comparison between experimental data and numerical modeling for the natural circulation phenomenon

Sabundjian, Gaiane; Andrade, Delvonei Alves de; Umbehaun, Pedro E.; Torres, Walmir M.; Macedo, Luiz A.; Conti, Thadeu das Neves; Mesquita, Roberto Navarro de; Angelo, Gabriel

doi:10.1590/s1678-58782011000500003

Cited by 14 publications

(10 citation statements)

References 5 publications

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“…Thus, in this section, a natural circulation experiment was simulated by the fully‐implicit numerical algorithm. The Sabundjian 35 natural circulation experiment was selected. The schematic drawing of the experimental circuit is shown in Figure 12.…”

Section: Validation With Two‐phase Flow Experimentsmentioning

confidence: 99%

A fully‐implicit numerical algorithm of two‐fluid two‐phase flow model using Jacobian‐free Newton–Krylov method

Fan

Gou

Huang

et al. 2022

Numerical Methods in Fluids

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Jacobian‐Free Newton–Krylov (JFNK) method is a stable and high‐efficiency method to solve the multi‐physics coupling problem for the modeling and simulation (M&S) of nuclear reactors. However, for the two‐fluid two‐phase flow model, the large number of constitutive models for different flow regimes as well as their discontinuities between different flow regimes present a huge challenge to solve the equations with JFNK method. Nevertheless, in this research, a fully‐implicit numerical algorithm was proposed to solve the two‐fluid two‐phase flow model based on the JFNK method. The field equations were fully‐implicitly discretized based on the second‐order backward time and Van Albada high‐order spatial difference schemes. A semi‐implicit‐scheme‐based preconditioner was constructed to improve the calculation efficiency. The V‐shaped linear advection test, water faucet test and the oscillating manometer test were simulated to evaluate the accuracy of the numerical algorithm and the performance of the numerical treatments with phase appearance and disappearance. By simulating the Bartolomei subcooled boiling experiment, Becker and Bennett dry out and post‐dry out experiments, the performances of the developed numerical algorithm for single‐phase flow, two‐phase flow and transition from the single‐phase flow to the two‐phase flow were validated. The single‐phase natural circulation and Edwards blowdown experiments were simulated to study the capability of the current fully‐implicit numerical algorithm for slow and quick transients, respectively. The results demonstrate good performance of the proposed algorithm and validate the accuracy of such algorithm. The comparisons of numerical efficiency show that the fully‐implicit numerical algorithm spends more time than the semi‐implicit numerical algorithm because the calculation of the inverse precondition matrix is time consuming. But the numerical stability of the fully‐implicit numerical algorithm is not influenced by the time step. In the practical simulations based on the fully‐implicit numerical algorithm, a large time step can be used to obtain a stable prediction and comparable or higher calculation efficiency and accuracy with respect to the semi‐implicit numerical algorithm.

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Section: Validation With Two‐phase Flow Experimentsmentioning

confidence: 99%

A fully‐implicit numerical algorithm of two‐fluid two‐phase flow model using Jacobian‐free Newton–Krylov method

Fan

Gou

Huang

et al. 2022

Numerical Methods in Fluids

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show abstract

“…In Brazil, single-phase NCLs were object of research of Sabundjian et al [15] and Angelo et al [3], which provided experimental and numerical data from single-and two-phase VHVC NCL test facilities, performed by the Institute of Energetic and Nuclear Research (IPEN), in São Paulo. Sabundjian et al [15] compared results from experiment and predictions obtained with RELAP5 system code. Good agreement was found by the authors.…”

Section: Short Reviewmentioning

confidence: 99%

Stability analysis of passive cooling systems for nuclear spent fuel pool

Lima

Mangiavacchi

Ferrari

2016

J Braz. Soc. Mech. Sci. Eng.

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which generate together 2000 MW. Angra 3, the third plant of the nuclear station, is under construction and will supply 1405 MW to the electrical grid. The nuclear fuel assemblies, after a work cycle, are removed from the reactor and stored in the respective storage pool. Each one of the NPPs is provided with a spent fuel pool, which has a limited storage capacity, and do not suffice for the whole lifetime of the plants. Thus, a complementary storage facility must be provided for the nuclear station for the NPPs to keep operation. Facilities for storage of spent fuel assemblies (SFAs) which are not "attached" to the reactor building are referred to as "away from reactor" storage facilities. There are two main types of SFA storage in away from reactor facilities: dry storage and wet storage. In both cases, the installation must be provided with a solution to the remove residual heat generated by the spent fuel.Eletronuclear, the company responsible for construction and operation of NPPs in Brazil, has designed a wet SFA storage facility to fulfill the demand for space. According to the design, this storage facility would be provided with a fully passive cooling system for removal of the residual heat. Worldwide, there is only one installation with a similar solution, which is operating in Gösgen, Switzerland. This decision follows the global trend to increase participation of passive systems in nuclear installations, especially after the events of March 11, 2011, in Fukushima. In that occasion three of the six units of Fukushima Daiichi nuclear station suffered a core meltdown caused by a lossof-coolant accident. The unavailability of external energy supply and emergency diesel generators was the cause for the loss of cooling capacity.Passive cooling systems (PCSs) are engineering solutions to perform the function of heat transfer using the temperature difference between hot and cold sources to generate the driving force for the flow. Their advantages

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“…As modificações possibilitaram estudos que geraram trabalhos publicados pela literatura técnica especializada (Andrade et al, 2005;Sabundjian et al, 2006Sabundjian et al, , 2007Sabundjian et al, , 2008Sabundjian et al, , 2009 eé neste contexto que este trabalho está inserido.…”

Section: Históricounclassified

Análise numérica da dinâmica do escoamento em circuitos de circulação natural

Angelo¹

Self Cite

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Ao Prof. Delvonei Alves de Andrade, orientador desta tese, exemplo de pesquisador e professor, com o qual passei muitos momentos aprendendo, discutindo e crescendo profissionalmente. Aos meus pais, a quem amo muito, cujo incentivo e apoio foram decisivos para a realização deste trabalho. Agradeço ao meu irmão, um exemplo de vida, um companheiro e um conselheiro nos momentos de dificuldade. A minha querida esposa Karina, sempre paciente e compreensiva. Ao Prof. Miguel Mattar Neto, um valioso colaborador, alguém de grande capacidade e visão. Sem os recursos fornecidos por ele a realização deste trabalho não seria possível. Ao pesquisador Pedro Ernesto Umbehaun, uma fonte de boas ideias e sugestões.

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Comparison between experimental data and numerical modeling for the natural circulation phenomenon

Cited by 14 publications

References 5 publications

A fully‐implicit numerical algorithm of two‐fluid two‐phase flow model using Jacobian‐free Newton–Krylov method

A fully‐implicit numerical algorithm of two‐fluid two‐phase flow model using Jacobian‐free Newton–Krylov method

Stability analysis of passive cooling systems for nuclear spent fuel pool

Análise numérica da dinâmica do escoamento em circuitos de circulação natural

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