Investigation of heat transfer characteristics of carbon dioxide transcritical flow in a reactor channel

IF 3.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Mao Luo , Hui Bao , Fulong Zhao , Ruibo Lu , Sichao Tan , Ruifeng Tian
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引用次数: 0

Abstract

The fourth generation of supercritical carbon dioxide (S-CO2) cooled advanced reactor has the characteristics of compact volume and high efficiency, and is widely used in space reactors and small reactors. For the purpose of the heat transfer characteristics of S-CO2 under transcritical conditions, the effects of changing inlet velocity, inlet CO2 fluid temperature, CO2 fluid operating pressure and wall heat flux on h and Nu in a single cylinder without gravity were analyzed by numerical simulation. The influence of different inlet flow rates on transcritical conditions under horizontal tube gravity is analyzed, and the temperature and velocity distributions of normal transcritical conditions and heat transfer deterioration conditions are compared. The consequence show that the rise of wall heat flux and the decrease of pressure will make the critical position move towards the inlet end. Reducing the inlet rate and increasing the inlet temperature will also shift the critical position towards the inlet end and result the heat transfer to worsen at the inlet end. In the horizontal pipe, when the heat transfer deteriorates, the CO2 fluid temperature differences between the top and lower parts exceeds 20 K, and the coefficient of heat transfer at underside is 2.5 times that at the top. When the deterioration degree of heat transfer deepens, the difference of heat transfer coefficients between the upper and lower parts of the channel will also increase due to ascent the temperature difference. Finally, the heat transfer deterioration can be attributed to the dual effects of the near-wall CO2 fluid criticality and the increase in the CO2 fluid mainstream thermal conductivity.
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来源期刊
Progress in Nuclear Energy
Progress in Nuclear Energy 工程技术-核科学技术
CiteScore
5.30
自引率
14.80%
发文量
331
审稿时长
3.5 months
期刊介绍: Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.
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