Conjugate heat transfer characteristics numerical simulation on steam generator tube of lead-cooled fast reactor-Reference-Cited by-同舟云学术

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Conjugate heat transfer characteristics numerical simulation on steam generator tube of lead-cooled fast reactor

Published:2024-02 Issue: Volume:417 Page:112841
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Qin Chong,Duan Wenshun,Zhang Kefan,Wang Weixiang,Dong Sifan,Chen Hongli

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

Reference28 articles.

1. Overview of lead-cooled fast reactor activities;Alemberti;Prog. Nucl. Ener.g,2014

2. A preliminary stability analysis of MYRRHA Primary Heat Exchanger two-phase tube bundle;Castelliti;Nucl. Eng. Des.,2016

3. Correlation for Boiling Heat Transfer to Saturated Fluids in Convective Flow;Chen;Ind. Eng. Chem. Process Des. Dev.,1966

4. Preliminary design of a medium-power modular lead-cooled fast reactor with the application of optimization methods;Chen;Int. J. Energ. Res.,2018

5. Experimental study on pressurization characteristics of a water droplet entrapped in molten LBE pool;Cheng;Nucl. Eng. Des.,2021

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