等高差被动安全壳冷却系统瞬态运行特性模拟研究

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
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引用次数: 0

摘要

被动安全壳冷却系统对于海洋核动力平台至关重要。本文重点研究了等高差自然循环被动安全壳冷却系统在两种启动策略下的瞬态特性。利用 APROS 软件建立了被动安全壳冷却系统的动态仿真模型。仿真结果表明,初始安全壳压力、初始不凝气含量和进水温度对压降率和自然循环流量有重要影响。空管启动模式与满管启动模式存在明显差异。在单相自然循环条件下,空管启动模式的压降率是满管启动模式的 3.1 倍以上,而在两相自然循环条件下,空管启动模式的压降率是满管启动模式的 1.5 倍以上,因为在满管启动模式下,自然循环中冷凝水引起的水锤导致两相流不稳定的波动幅度较大。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Simulation study on the transient operating characteristics of equal height difference passive containment cooling system

The passive containment cooling system is crucial important for marine nuclear power platform. This paper focuses on the transient characteristic of passive containment cooling system with equal height difference natural circulation under two starting strategy. Dynamic simulation model of passive containment cooling system is set up with APROS software. The simulation results indicate that the initial containment pressure, initial non-condensable gas content, and inlet water temperature have important effects on the pressure drop rate and natural circulation flow rate. And obvious differences exist between the empty tube starting mode and the full tube starting mode. Under single-phase natural circulation conditions, the pressure drop rate of the empty tube starting mode is more than 3.1 times that of the full tube starting mode, while under two-phase natural circulation conditions, the pressure drop rate of the empty tube starting mode is more than 1.5 times that of the full tube starting mode, since large fluctuation amplitude of two-phase flow instability caused by condensation induced water hammer in the natural circulation occurs under full tube starting mode.

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来源期刊
Annals of Nuclear Energy
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.
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