Experimental study on thermal-hydraulic performance of helically coiled tubes steam generator of lead-bismuth reactor-Reference-Cited by-同舟云学术

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Experimental study on thermal-hydraulic performance of helically coiled tubes steam generator of lead-bismuth reactor

Published:2024-03 Issue:1 Volume:6 Page:32-42
ISSN:2468-6050
Container-title:International Journal of Advanced Nuclear Reactor Design and Technology
language:en
Short-container-title:International Journal of Advanced Nuclear Reactor Design and Technology

Author:

Gu Dandan,Zhu Lina,Xiao Changzhi,Yang Hongyi

Publisher

Elsevier BV

Reference7 articles.

1. Experimental study of flow boiling heat transfer and dryout characteristics at low mass flux in helically-coiled tubes;Hwanga;Nucl. Eng. Des.,2014

2. Study on critical heat flux of steam-water two-phase flow in helical coil tubes;Bi;Journal of Xi’an Jiao Tong University,1996

3. Experimental investigation of boiling heat transfer in helically coiled tubes at high pressure;Xiao;Ann. Nucl. Energy,2018

4. Investigation of heat and mass transferin helical coil and AlFregime prediction model;Xiao;Atomic Energy Sci. Technol.,2022

5. An experimental study on subcooled flow boiling heat transfer characteristics of Rl34a in vertical helically coiled tubes;Kong;Exp. Therm. Fluid Sci.,2017

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