• Title/Summary/Keyword: Nuclear Project

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MULTI-SCALE MODELING AND ANALYSIS OF CONVECTIVE BOILING: TOWARDS THE PREDICTION OF CHF IN ROD BUNDLES

  • Niceno, B.;Sato, Y.;Badillo, A.;Andreani, M.
    • Nuclear Engineering and Technology
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    • v.42 no.6
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    • pp.620-635
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    • 2010

  • 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.

  • https://doi.org/10.5516/NET.2010.42.6.620 인용 PDF KSCI

Issues of New Technological Trends in Nuclear Power Plant (NPPs) for Standardized Breakdown Structure

  • Gebremichael, Dagem D.;Lee, Yunsub;Jung, Youngsoo
    • International conference on construction engineering and project management
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    • 2020.12a
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    • pp.353-358
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    • 2020

  • Recent efforts to develop a common standard for nuclear power plants (NPPs) with the aim of creating (1) a digital environment for a better understanding of NPPs life-cycle management aspect and (2) engineering data interoperability by using existing standards among different unspecified project participants (e.g., owners/operators, engineers, contractors, equipment suppliers) during plants' life cycle process (EPC, O&M, and decommissioning). In order to meet this goal, there is a need for formulating a standardized high-level physical breakdown structure (PBS) for NPPs project management office (PMO). However, high-level PBS must be comprehensive enough and able to represent the different types of plants and the new trends of technologies in the industry. This has triggered the need for addressing the issues of the recent operational NPPs and future technologies' ramification for evaluating the changes in the NPPs physical components in terms of structure, system, and component (SSC) configuration. In this context, this ongoing study examines the recent conventional NPPs and technological trends in the development of future NPPs facilities. New reactor models regarding the overlap of variant issues of nuclear technology were explored. Finally, issues on PBS for project management are explored by the examination of the configuration of NPPs primary system. The primary systems' configuration of different reactor models is assessed in order to clarify the need for analyzing the new trends in nuclear technology and to formulate a common high-level PBS. Findings and implications are discussed for further studies.

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Development of Safety Management System Based on Location Determination Technology for Construction Workers in Nuclear Power Plant Construction Project (무선측위 기술을 활용한 원전 건설현장 인원 안전관리 시스템 개발 방안)

  • KIM, WooJoong;Lee, Sang-Hyun
    • Proceedings of the Korean Institute of Building Construction Conference
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    • 2016.05a
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    • pp.239-240
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    • 2016

  • The nuclear power plant construction project is a large-scale project that involved a daily maximum of thousands of workers. many equipment and laborers involved has been required consistently to minimize the need for safety through real-time safety management. But current nuclear power plant construction site is only managed to access of workers and equipments. The purpose of this study is the owner requirements reflects the characteristics of the nuclear power plant construction project integrated safety management system utilizing active RFID and GPS positioning technology.

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