Research on thermal hydraulic characteristics of integrated reactor in natural circulation operation under ocean motions-Reference-Cited by-同舟云学术

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Research on thermal hydraulic characteristics of integrated reactor in natural circulation operation under ocean motions

Published:2020-08 Issue: Volume:126 Page:103399
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Jianbang Wu,Mingguang Zheng,Minglu Wang,Shufeng Zhao,Xiangyun Zhang

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference16 articles.

1. Correlation for boiling heat transfer to saturated fluids in convective flow[J];Chen;Ind. Eng. Chem. Process Des. Dev.,1966

2. Development and validation of nuclear reactor thermal-hydraulic system analysis code under ocean conditions[J];Cheng;J. Harbin Eng. Univ.,2017

3. Two-phase pressure drop prediction in helically coiled steam generators for nuclear power applications[J];Cioncolini;Int. J. Heat Mass Tran.,2016

4. The Feynman Lectures on Physics[M];Feynman,2003

5. Heat transfer and pressure drop for cross flow through banks of multistart helical tubes with uniform inclinations and uniform longitudinal pitches[J];Gilli;Nucl. Sci. Eng.,1965

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1. Numerical study on flow characteristics in the primary side of a once-through steam generator under ocean conditions;Frontiers in Energy Research;2024-02-07

2. Numerical simulation of the early startup period of heat pipe cooled reactor system from the room temperature state;Annals of Nuclear Energy;2024-01

3. Numerical simulation of microchannel flow boiling and critical heat flux under rolling motion;International Journal of Refrigeration;2023-01

4. Study of density wave instability in natural circulation with parallel channels under inclined and heaving conditions;Progress in Nuclear Energy;2023-01

5. Numerical Simulation of the Early Startup Period of Heat Pipe Cooled Reactor System from the Room Temperature State;2023

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