Improvement of the subcooled boiling model for thermal–hydraulic system codes-Reference-Cited by-同舟云学术

Improvement of the subcooled boiling model for thermal–hydraulic system codes

Published:2020-08 Issue: Volume:364 Page:110641
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Ha Tae-Wook,Yun Byong-Jo,Jeong Jae Jun

Funder

National Research Foundation of Korea

Korea Foundation

Nuclear Safety and Security Commission

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

Reference42 articles.

1. Experimental study of true void fraction when boiling subcooled water in vertical tubes;Bartolomei;Therm. Eng.,1967

2. Experimental investigation of void fraction at subcooled boiling mode in tubes;Bartolomei;Teploenergetika,1982

3. Experimental Data Report for LOFT Large Break LOCA;Bayless;Experiment,1982

4. Introduction to heat transfer;Bergman,2011

5. Bibeau, E.L., 1988. Experimental investigation of subcooled void growth for upflow and downflow at low velocities and low pressure. PhD Thesis, University of British Columbia, Vancouver, BC.

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