European activities on crosscutting thermal-hydraulic phenomena for innovative nuclear systems
| Autor: | Weimin Ma, Uwe Hampel, M. Prasser, K. Van Tichelen, A. Papukchiev, Xu Cheng, A. Gerschenfeld, Ferry Roelofs, Abdalla Batta, Giacomino Bandini |
|---|---|
| Přispěvatelé: | Bandini, G. |
| Jazyk: | angličtina |
| Rok vydání: | 2015 |
| Předmět: |
Engineering
MRI matching refractive index SFR sodium-cooled fast reactor DHR decay heat removal Mechanical engineering THINS thermal-hydraulics of innovative nuclear system MSR molten salt reactor General Materials Science Single phase Safety Risk Reliability and Quality HLM heavy liquid metal Waste Management and Disposal LBE lead bismuth eutectic ADS accelerator-driven subcritical nuclear systems media_common HTR high temperature reactor VHTR very high temperature reactor SC supercritical LDA laser Doppler anemometry DNS direct numerical simulation SCWR supercritical water cooled reactor ADS accelerator-driven subcritical nuclear system Systems engineering LFR lead-cooled fast reactor Nuclear and High Energy Physics Design analysis RANS Reynolds-averaged Navier-Stokes equation THINS thermal-hydraulics of innovative nuclear systems PTV particle tracking velocimetry ComputerApplications_COMPUTERSINOTHERSYSTEMS GFR gas-cooled fast reactor Thermal hydraulics LES large eddy simulation media_common.cataloged_instance Engineering tool European union RANS Reynolds-averaged Navier-Stokes equations CFD computational fluid dynamic business.industry Mechanical Engineering GIF Gen-IV International Forum CFD computational fluid dynamics LMR liquid metal reactors Code coupling Nuclear Energy and Engineering Nuclear reactor core LMR liquid metal reactor Key (cryptography) business |
| Zdroj: | Nuclear Engineering and Design 290(2015), 2-12 |
| Popis: | Thermal-hydraulics is recognized as a key scientific subject in the development of innovative reactor systems. In Europe, a consortium is established consisting of 24 institutions of universities, research centers and nuclear industries with the main objectives to identify and to perform research activities on important crosscutting thermal-hydraulic issues encountered in various innovative nuclear systems. For this purpose the large-scale integrated research project THINS (Thermal-Hydraulics of Innovative Nuclear Systems) is launched in the 7th Framework Programme FP7 of European Union. The main topics considered in the THINS project are (a) advanced reactor core thermal-hydraulics, (b) single phase mixed convection, (c) single phase turbulence, (d) multiphase flow, and (e) numerical code coupling and qualification. The main objectives of the project are:Generation of a data base for the development and validation of new models and codes describing the selected crosscutting thermal-hydraulic phenomena.Development of new physical models and modeling approaches for more accurate description of the crosscutting thermal-hydraulic phenomena.Improvement of the numerical engineering tools for the design analysis of the innovative nuclear systems. This paper describes the technical tasks and methodologies applied to achieve the objectives. Main results achieved so far are summarized. This paper serves also as a guidance of this special issue. © 2014 Elsevier B.V. All rights reserved. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
|