Critical Heat Flux of Flowing Water in Tube for Pressure Up to Near Critical Point—Experiment and Prediction-Reference-Cited by-同舟云学术

Critical Heat Flux of Flowing Water in Tube for Pressure Up to Near Critical Point—Experiment and Prediction

Published:2017-12-04 Issue:1 Volume:4 Page:
ISSN:2332-8983
Container-title:Journal of Nuclear Engineering and Radiation Science
language:en
Short-container-title:

Author:

Chen Yuzhou¹,Zhao Minfu¹,Bi Keming¹,Yang Bin¹,Zhang Dongxu²,Du Kaiwen¹

Affiliation:

1. Department of Reactor Engineering Research and Design, China Institute of Atomic Energy, P.O. Box 275(59), Beijing 102413, China e-mail:

2. Department of Reactor Engineering Research and Design, China Institute of Atomic Energy,P.O. Box 275(59), Beijing 102413, China e-mail:

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

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Link

http://asmedigitalcollection.asme.org/nuclearengineering/article-pdf/doi/10.1115/1.4038215/6068502/ners_004_01_011006.pdf

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