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contributor authorYang, Dong
contributor authorChen, Jiaxiang
contributor authorFeng, Yongchang
contributor authorChen, Lin
date accessioned2022-05-08T08:30:59Z
date available2022-05-08T08:30:59Z
date copyright10/19/2021 12:00:00 AM
date issued2021
identifier issn2332-8983
identifier otherners_008_02_021402.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4284025
description abstractThermal efficiency and safety of generation-IV nuclear-power-reactor concept supercritical water-cooled reactor (SCWR) are largely dependent on the coupled supercritical water (SCW) thermophysical properties and heat transfer performance in the supercritical region. This paper presents the numerical investigation of the heat-transfer characteristics of SCW flow in a 4-m long circular tube (ID = 10 mm) based on computational fluid dynamics. Numerical model for SCW was established in this analysis and forced-convection heat transfer was studied at different operating conditions. The data were collected at pressure of about 24 MPa, inlet temperatures from 320 to 350 °C, mass flux from 1000 to 1500 kg/m2·s, and heat flux up to 1500 kW/m2. Results of numerical simulation predict the experimental data with reasonable accuracy. A dimensional analysis was conducted to derive the general form of an empirical supercritical water heat-transfer correlation. The decrease of turbulent viscosity due to the decrease of density leads to a lower turbulent diffusion and turbulent kinetic energy, which inhibits heat transfer. The increased wall temperature and localized heat transfer deterioration (HTD) would occur as the liquid in the core of the tube is isolated for the low-density fluid adheres to the near-wall region, which is characterized by low thermal capacity.
publisherThe American Society of Mechanical Engineers (ASME)
titleNumerical Verifications on Heat Transfer to Supercritical Water Flowing Upward in a 4-m Long Bare Vertical Tube
typeJournal Paper
journal volume8
journal issue2
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4051248
journal fristpage21402-1
journal lastpage21402-11
page11
treeJournal of Nuclear Engineering and Radiation Science:;2021:;volume( 008 ):;issue: 002
contenttypeFulltext


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