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contributor authorChen, Yuzhou
contributor authorZhao, Minfu
contributor authorBi, Keming
contributor authorYang, Bin
contributor authorZhang, Dongxu
contributor authorDu, Kaiwen
date accessioned2019-02-28T11:05:21Z
date available2019-02-28T11:05:21Z
date copyright12/4/2017 12:00:00 AM
date issued2018
identifier issn2332-8983
identifier otherners_004_01_011006.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252549
description abstractCritical heat flux (CHF) experiment with uniform heating was performed in a tube of 8.2 mm in inner diameter and 2.4 m in heated length. The water flowed upward through the test section. The pressure covered the range from 8.6 to 20.8 MPa, mass flux 1157 to 3776 kg/m2s, inlet quality −2.79 to −0.08 (subcooling 19–337 °C), and local quality −0.97 to 0.53. For the pressure close to the near-critical point, the CHF decreased substantially with the pressure increasing. For the subcooling larger than a certain value, the CHF was related to the local condition. But for low subcooling and saturated condition, the CHF was related to the total power. The present results were in agreement with the previous experiment for the same local subcooled condition. Based on the present experimental results with subcooled and saturated conditions an empirical relation of the CHF was presented.
publisherThe American Society of Mechanical Engineers (ASME)
titleCritical Heat Flux of Flowing Water in Tube for Pressure Up to Near Critical Point—Experiment and Prediction
typeJournal Paper
journal volume4
journal issue1
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4038215
journal fristpage11006
journal lastpage011006-5
treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 001
contenttypeFulltext


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