Numerical simulation of the flow flashing of carbon dioxide in a circular pipe

IF 3.2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Progress in Nuclear Energy Pub Date : 2026-03-01 Epub Date: 2025-12-31 DOI:10.1016/j.pnucene.2025.106224
Wukun Zhu, Han Wang, Fanghao Chen, Jinghui Wu
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引用次数: 0

Abstract

The study of Loss of Coolant Accidents (LOCA) in supercritical carbon dioxide (S-CO2) reactors constitutes a critical and challenging domain in nuclear safety analysis, with the investigation of flow flashing phenomena in pipelines being particularly pivotal. In this work, reactor pipelines were simplified, and a transient numerical simulation code for channel flow flashing was developed based on the homogeneous flow model, integrated with a suite of relevant correlations. Computational results from this code were validated against experimental data for water flow flashing, showing strong consistency with the measured values. Specifically, the maximum error in predicting flash onset (the point where vapor first forms) was approximately 5 %, thereby confirming the model accuracy. Utilizing the validated code, an in-depth analysis of the flow flashing process with CO2 as the working fluid was conducted. For vertical pipes, higher inlet fluid temperature, lower outlet pressure, and lower inlet velocity were found to extend the length of the flashing two-phase region and increase the outlet void fraction. Furthermore, transient depressurization processes at the outlets of vertical pipes were numerically simulated to verify the code's transient analysis capabilities. For horizontal pipes, lower inlet pressure triggers adiabatic flashing, resulting in higher steam quality. Faster outlet depressurization initiates earlier flashing, enhances volume expansion, accelerates flow velocity, and elevates the peak mass flow rate. Overall, the computational results provide a solid theoretical foundation for LOCA analysis in S-CO2 reactors.
二氧化碳在圆管内流动闪蒸的数值模拟
超临界二氧化碳(S-CO2)反应堆冷却剂损失事故(LOCA)的研究是核安全分析中的一个关键和具有挑战性的领域,其中管道流动闪蒸现象的研究尤为关键。本文对反应器管道进行了简化,并基于均匀流动模型开发了通道闪蒸瞬态数值模拟程序。通过对水流闪蒸试验数据的验证,计算结果与实测值具有较强的一致性。具体来说,预测闪光开始(蒸汽首次形成的点)的最大误差约为5%,从而证实了模型的准确性。利用验证后的程序,对以CO2为工质的流动闪蒸过程进行了深入分析。对于垂直管道,较高的进口流体温度、较低的出口压力和较低的进口速度可以延长闪蒸两相区长度,增加出口空隙率。此外,还对垂直管道出口的瞬态降压过程进行了数值模拟,以验证该程序的瞬态分析能力。对于水平管道,较低的进口压力触发绝热闪蒸,导致更高的蒸汽质量。更快的出口减压启动了更早的闪蒸,增强了体积膨胀,加速了流速,提高了峰值质量流量。计算结果为S-CO2反应器的LOCA分析提供了坚实的理论基础。
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
Progress in Nuclear Energy
Progress in Nuclear Energy 工程技术-核科学技术
CiteScore
5.30
自引率
14.80%
发文量
331
审稿时长
3.5 months
期刊介绍: Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.
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