Prediction of critical heat flux in non-uniform heated rod bundle based on modified CHF empirical correlations-Reference-Cited by-同舟云学术

Prediction of critical heat flux in non-uniform heated rod bundle based on modified CHF empirical correlations

Published:2024-02 Issue: Volume:417 Page:112875
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Zhu Gan,Wang Zhuang,Xie Heng

Funder

China National Nuclear Corporation

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

Reference22 articles.

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3. Bowring, R.W. WSC-2, A subchannel dryout correlation for water-cooled cluster over the pressure range 3.4 – 15.9 MPa (500 – 2300 psia), Technical Report AEEWR983, Winfrith, UK, 1979.

4. Review on critical heat flux in water cooled reactors;Cheng;Wissenschaftliche Berichte Fzka,2003

5. Faya, A., Wolf, L., Todreas, N.E. Development of a method for BWR subchannel analysis. 1979.

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