contributor author | Chen, Yuzhou | |
contributor author | Zhao, Minfu | |
contributor author | Bi, Keming | |
contributor author | Yang, Bin | |
contributor author | Zhang, Dongxu | |
contributor author | Du, Kaiwen | |
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_011006.pdf | |
identifier uri | http://yetl.yabesh.ir/yetl1/handle/yetl/4252549 | |
description abstract | Critical 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. | |
publisher | The American Society of Mechanical Engineers (ASME) | |
title | Critical Heat Flux of Flowing Water in Tube for Pressure Up to Near Critical Point—Experiment and Prediction | |
type | Journal Paper | |
journal volume | 4 | |
journal issue | 1 | |
journal title | Journal of Nuclear Engineering and Radiation Science | |
identifier doi | 10.1115/1.4038215 | |
journal fristpage | 11006 | |
journal lastpage | 011006-5 | |
tree | Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 001 | |
contenttype | Fulltext | |