Characteristics of critical heat flux under rolling condition for flow boiling in vertical tube-Reference-Cited by-同舟云学术

Characteristics of critical heat flux under rolling condition for flow boiling in vertical tube

Published:2012-11 Issue: Volume:252 Page:153-162
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Hwang Jin-Seok,Lee Yeon-Gun,Park Goon-Cherl

Funder

National Research Foundation of Korea

Ministry of Education, Science and Technology

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

Reference17 articles.

1. Heat transfer in saturated boiling;Chang,1997

2. Dix, C.E., 1971. Vapor void fractions for forced convection with subcooled boiling at low flow rates. Ph.D. Thesis.

3. A phenomenological prediction of dryout based on the churn-to-annular flow transition criterion in uniformly heated vertical tubes;Hong,2000

4. Assessment of MARS code for predicting critical heat flux under heaving conditions;Hwang;Nucl. Technol.,2011

5. Effect of heaving and a listing upon thermo hydraulic performance and critical heat flux of water-cooled marine reactors;Isshiki;Nucl. Eng. Des.,1965

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