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RISS 인기검색어
- 검색키워드
- 저자 : Niceno, B. (검색결과 3 건)
- 무료
- 기관 내 무료
- 유료
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Niceno, B.,Sato, Y.,Badillo, A.,Andreani, M. Korean Nuclear Society 2010 Nuclear Engineering and Technology Vol.42 No.6
In this paper we describe current activities on the project Multi-Scale Modeling and Analysis of convective boiling (MSMA), conducted jointly by the Paul Scherrer Institute (PSI) and the Swiss Nuclear Utilities (Swissnuclear). The long-term aim of the MSMA project is to formulate improved closure laws for Computational Fluid Dynamics (CFD) simulations for prediction of convective boiling and eventually of the Critical Heat Flux (CHF). As boiling is controlled by the competition of numerous phenomena at various length and time scales, a multi-scale approach is employed to tackle the problem at different scales. In the MSMA project, the scales on which we focus range from the CFD scale (macro-scale), bubble size scale (meso-scale), liquid micro-layer and triple interline scale (micro-scale), and molecular scale (nano-scale). The current focus of the project is on micro- and meso-scales modeling. The numerical framework comprises a highly efficient, parallel DNS solver, the PSI-BOIL code. The code has incorporated an Immersed Boundary Method (IBM) to tackle complex geometries. For simulation of meso-scales (bubbles), we use the Constrained Interpolation Profile method: Conservative Semi-Lagrangian $2^{nd}$ order (CIP-CSL2). The phase change is described either by applying conventional jump conditions at the interface, or by using the Phase Field (PF) approach. In this work, we present selected results for flows in complex geometry using the IBM, selected bubbly flow simulations using the CIP-CSL2 method and results for phase change using the PF approach. In the subsequent stage of the project, the importance of effects of nano-scale processes on the global boiling heat transfer will be evaluated. To validate the models, more experimental information will be needed in the future, so it is expected that the MSMA project will become the seed for a long-term, combined theoretical and experimental program.
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B. NICENO,Y. SATO,A. BADILLO,M. ANDREANI 한국원자력학회 2010 Nuclear Engineering and Technology Vol.42 No.6
In this paper we describe current activities on the project Multi-Scale Modeling and Analysis of convective boiling (MSMA),conducted jointly by the Paul Scherrer Institute (PSI) and the Swiss Nuclear Utilities (Swissnuclear). The long-term aim ofthe MSMA project is to formulate improved closure laws for Computational Fluid Dynamics (CFD) simulations for predictionofconvective boiling and eventually of the Critical Heat Flux (CHF). As boiling is controlled by the competitionof numerousphenomena at various length and time scales, a multi-scale approach is employed to tackle the problem at different scales. Inthe MSMA project, the scales on which we focus range from the CFD scale (macro-scale), bubble size scale (meso-scale),liquid micro-layer and triple interline scale (micro-scale), and molecular scale (nano-scale). The current focus of the projectis on micro- and meso- scales modeling. The numerical framework comprises a highly efficient, parallel DNS solver, thePSI-BOIL code. The code has incorporated an Immersed Boundary Method (IBM) to tackle complex geometries. For simulationof meso-scales (bubbles), we use the Constrained Interpolation Profile method: Conservative Semi-Lagrangian 2ndorder(CIP-CSL2). The phase change is described either by applying conventional jump conditions at the interface, or by using thePhase Field (PF) approach. In this work, we present selected results for flows in complex geometry using the IBM, selectedbubbly flow simulations using the CIP-CSL2 method and results for phase change using the PF approach. In the subsequentstage of the project, the importance of effects of nano-scale processes on the global boiling heat transfer will be evaluated.To validate the models, more experimental information will be needed in the future, so it is expected that the MSMA projectwill become the seed for a long-term, combined theoretical and experimental program.
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CFD study of the PTS experiment in ROCOM test facility
Carija, Zoran,Ledic, Fran,Sikirica, Ante,Niceno, Bojan Korean Nuclear Society 2020 Nuclear Engineering and Technology Vol.52 No.12
With the aging of nuclear reactors, embrittlement of the reactor pressure vessel (RPV) steel, as a consequence of routine operations, is highly probable. To ensure operational integrity and safety, prediction and mitigation of compromising damage, brought on by pressurized thermal shock (PTS) following an emergency procedure, is of utmost importance. Computational fluid dynamics (CFD) codes can be employed to predict these events and have therefore been an acceptable method for such assessments. In this paper, CFD simulations of a density driven ECC state in the ROCOM facility are analyzed. Obtained numerical results are validated with the experimental measurements. Considerable attention is attributed to the boundary conditions and their influence, specifically outlet definitions, in order to determine and adequately replicate the non-active pumps in the facility. Consequent analyses focused on initial conditions as well as on the temporal discretization and inner iterations. Disparities due to different turbulent modelling approaches are investigated for standard RANS models. Based on observed trends for different cases, a definitive simulation setup has been established, results of which have been ultimately compared to the measurements.
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