The Basic Thermal Hydraulic Issues of Applying Supercritical Fluid to Nuclear Reactors

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Author(s): Jinguang Zang (Nuclear Power Institute of China, China), Xiao Yan (Nuclear Power Institute of China, China)and Yanping Huang (Nuclear Power Institute of China, China)
Copyright: 2021
Pages: 35
Source title: Handbook of Research on Advancements in Supercritical Fluids Applications for Sustainable Energy Systems
Source Author(s)/Editor(s): Lin Chen (Institute of Engineering Thermophysics, Chinese Academy of Sciences, China & University of Chinese Academy of Sciences, China)
DOI: 10.4018/978-1-7998-5796-9.ch019

Keywords: Chemical Engineering / Engineering Science Reference / Science & Engineering

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Abstract

This chapter is mainly focused on illustrating some introductory progress on thermal hydraulic issues of supercritical water, including heat transfer characteristics, pressure loss characteristics, flow stability issues, and numerical method. These works are mainly to give a basic idea of elementary but important topics in this area. An analytical method was proposed up to predict the heat transfer coefficient and friction coefficient based on the two-layer wall function. Flow instability experiments have been carried out in a two-parallel-channel system with supercritical water, aiming to provide an up-to-date knowledge of supercritical flow instability phenomena and initial validation data for numerical analysis. The natural circulation instability of supercritical water was also investigated in the experiments.

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The Basic Thermal Hydraulic Issues of Applying Supercritical Fluid to Nuclear Reactors

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