液态金属快堆螺旋盘管直通式蒸汽发生器热液压特性的稳态和瞬态分析

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

摘要

基于全局离散网格法,建立了液态金属快堆螺旋盘管直通式蒸汽发生器(HCOTSG)的热液特性瞬态模型。该模型对液态金属回路和水-蒸汽回路进行了网格划分。同时,建立了非稳态热传导方程,以精确模拟两侧的耦合传热。水-蒸汽流动采用四方程漂移-通量法。以铅铋快堆为例,首先计算了稳定工况下 HCOTSG 的热工水力特性。结果发现,沿蒸汽发生器的热通量分布极不均匀,壁面热通量最大值与最小值相差达数百倍。然后,模拟了一次侧入口条件受到阶跃变化扰动时的瞬态响应,发现当入口铅铋温度阶跃从 450°C 增加到 480°C 时,最大壁面热通量从 1175.5 kW/m2 增加到 1365 kW/m2,增加了近 16%。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Steady and transient analysis on thermal hydraulic characteristic of helical coiled once-through steam generator of liquid metal fast reactor

A transient model for thermal–hydraulic characteristics of helical coiled once-through steam generator (HCOTSG) of liquid metal fast reactor was established based on global discrete grid method. The model meshed the liquid metal circuit and water-steam circuit. Meanwhile, unsteady heat conduction equations were built to accurately simulate coupled heat transfer between two sides. Four-equation drift-flux method was adopt for water-steam flow. Taking lead–bismuth fast reactor as example, thermal–hydraulic characteristics of HCOTSG were first calculated under steady conditions. It was found that heat flux distribution along steam generator is extremely uneven, and the difference between maximum and minimum wall heat flux reaches hundreds of times. Then, the transient response was simulated when inlet conditions of primary side were perturbed by step changes, and it was found that maximum wall heat flux increases from 1175.5 kW/m2 to 1365 kW/m2, increasing by nearly 16 %, when inlet lead–bismuth temperature step increases from 450°C to 480 °C.

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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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