Critical heat fluxes of subcooled water flow boiling in a short vertical tube at high liquid Reynolds number-Reference-Cited by-同舟云学术

Critical heat fluxes of subcooled water flow boiling in a short vertical tube at high liquid Reynolds number

Published:2010-10 Issue:10 Volume:240 Page:3145-3157
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Hata Koichi,Masuzaki Suguru

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference35 articles.

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