Research Challenges of Heat Transfer to Supercritical FluidsSource: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 001::page 11003DOI: 10.1115/1.4037117Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Supercritical fluids (SCFs) become more and more important in various engineering applications. In nuclear power systems, SCFs are considered as coolant of the reactor core such as the supercritical water-cooled reactor (SCWR), superconducting magnets and blankets in the fusion reactors, or as fluid in the energy conversion systems of the next generation nuclear reactors. Accurate determination of heat transfer and the temperature of the structural material (e.g., fuel rod cladding) is of crucial importance for the system design. Thus, extensive studies on heat transfer to SCFs have been carried out in the past five decades and are still ongoing worldwide. However, no breakthrough is recognized or expected in the near future. In this paper, the status, main challenges, and future R&D needs are briefly reviewed. Three aspects are taken into consideration, i.e., experimental studies, numerical analysis, and model development for the prediction of heat transfer coefficient (HTC). Several key challenges and also the important subjects of the future R&D needs are identified. They are (a) data base for turbulence quantities, (b) multisolution of wall temperature, (c) extensive Reynolds-averaged Navier–Stokes (ERANS) method, and (d) new prediction method for HTC.
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contributor author | Cheng, X. | |
contributor author | Liu, X. J. | |
date accessioned | 2019-02-28T11:05:21Z | |
date available | 2019-02-28T11:05:21Z | |
date copyright | 12/4/2017 12:00:00 AM | |
date issued | 2018 | |
identifier issn | 2332-8983 | |
identifier other | ners_004_01_011003.pdf | |
identifier uri | http://yetl.yabesh.ir/yetl1/handle/yetl/4252551 | |
description abstract | Supercritical fluids (SCFs) become more and more important in various engineering applications. In nuclear power systems, SCFs are considered as coolant of the reactor core such as the supercritical water-cooled reactor (SCWR), superconducting magnets and blankets in the fusion reactors, or as fluid in the energy conversion systems of the next generation nuclear reactors. Accurate determination of heat transfer and the temperature of the structural material (e.g., fuel rod cladding) is of crucial importance for the system design. Thus, extensive studies on heat transfer to SCFs have been carried out in the past five decades and are still ongoing worldwide. However, no breakthrough is recognized or expected in the near future. In this paper, the status, main challenges, and future R&D needs are briefly reviewed. Three aspects are taken into consideration, i.e., experimental studies, numerical analysis, and model development for the prediction of heat transfer coefficient (HTC). Several key challenges and also the important subjects of the future R&D needs are identified. They are (a) data base for turbulence quantities, (b) multisolution of wall temperature, (c) extensive Reynolds-averaged Navier–Stokes (ERANS) method, and (d) new prediction method for HTC. | |
publisher | The American Society of Mechanical Engineers (ASME) | |
title | Research Challenges of Heat Transfer to Supercritical Fluids | |
type | Journal Paper | |
journal volume | 4 | |
journal issue | 1 | |
journal title | Journal of Nuclear Engineering and Radiation Science | |
identifier doi | 10.1115/1.4037117 | |
journal fristpage | 11003 | |
journal lastpage | 011003-7 | |
tree | Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 001 | |
contenttype | Fulltext |