High-parameter multiphase critical flow in supercritical carbon dioxide nuclear energy system

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-09-13 DOI:10.1016/j.anucene.2025.111878

Gengyuan Tian , Yuan Zhou , Yanping Huang , Yuan Yuan , Chengtian Zeng , Shuai Liu

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引用次数: 0

Abstract

The loss-of-coolant accident (LOCA) is one of the major safety concerns in the supercritical carbon dioxide power cycle system. The precise calculation of critical flow rate during LOCA is of paramount significance as it determines the rate of coolant loss in the system. In this paper, a set of simple regenerative power cycle experimental apparatus was established, and research on high-parameter (maximum pressure:15.0 MPa, maximum temperature:500.0 °C) critical flow was carried out. The influence of thermal parameters and geometric parameters on critical flow rate was analyzed. A theoretical model of critical flow that accounts for thermal non − equilibrium phase transition and variation of the compressibility has been developed. The model accurately predicts supercritical CO₂ critical flow rates across wide parameters, with under 10 % error. The experimental data and theoretical model obtained in this research can be utilized for the safety analysis of supercritical CO₂ power cycle systems.

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超临界二氧化碳核能系统的高参数多相临界流

失冷剂事故是超临界二氧化碳动力循环系统的主要安全问题之一。失稳临界流量的精确计算决定了系统中冷却剂的损失率，具有至关重要的意义。本文建立了一套简易蓄热式电力循环实验装置，进行了高参数（最大压力：15.0 MPa，最高温度：500.0℃）临界流量研究。分析了热参数和几何参数对临界流量的影响。建立了一个考虑热非平衡相变和可压缩性变化的临界流动理论模型。该模型能准确预测超临界CO2临界流量，误差在10%以下。本研究获得的实验数据和理论模型可用于超临界CO2动力循环系统的安全性分析。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

期刊介绍： Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.