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首页> 外文会议>International Conference on Nuclear Engineering: Abstracts >BUBBLE BEHAVIOR IN TWO-PHASE FLOW NATURALCIRCULATION EMPLOYED IN THE PRIMARY SYSTEMON THE INTEGRATED MODULAR WATER REACTOR (IMR),ANALYZED BY α-FLOW CODE
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BUBBLE BEHAVIOR IN TWO-PHASE FLOW NATURALCIRCULATION EMPLOYED IN THE PRIMARY SYSTEMON THE INTEGRATED MODULAR WATER REACTOR (IMR),ANALYZED BY α-FLOW CODE

机译：集成模块式水反应器（IMR）主系统中应用的两相流自然循环中的气泡行为，通过α-流代码进行分析

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The Integrated Modular Water Reactor (IMR) isone of the advanced small-sized reactors. Its rectorvessel features the primary cooling system employingtwo-phase flow natural circulation of light watercoolant and built-in-vessel type of steam generators.This primary cooling system, named the Hybrid HeatTransport System (HHTS), enables competitiveeconomy and high-level safety by elimination ofpiping of large diameter, pumps and pressurizers. Thesteam generators are two kinds; one (SGV) is locatedin the vapor region in the reactor vessel to condensevapor and control the primary system pressure, theother (SGL) is submerged in the two-phase mixtureregion to remove heat from the mixture and controlthe core inlet temperature down to subcooled state.The SGV and SGL totally extract 1000MW of thermalpower from the core. The design target of averagedvoid fraction in the two-phase upward flow is around20% to 25 %, which is corresponding to bubbly flow.The performance of the HHTS is subject to bubble behavior and void distribution in the circulation. Thisstudy deals with bubble behavior investigation for theriser-downcomer sections through analyses by thecommercial code, α-FLOW. Free surface vaporseparation from the two-phase flow, which isimportant to determine required capacities of the SGVand the SGL, is also estimated, and vapor separationon the steam-water simulation test with the loopfacility of small diameter piping is additionallyinvestigated to clarify its predominant factors of theseparation. The analyses show two-phase flowdistributions dependent to the given conditions at theriser inlet, which are corresponding to core cycleburn-ups. The analyses estimate around 30% of thegenerated vapor to separate up to the vapor region inthe case of 16GWd/t of cycle burn-up without theinternal structures, while the steam-water simulationtest data arranged by the induced velocity parametersuggest that predominant factors of the vaporseparation are the system pressure and liquid velocityhorizontally flowing towards the downcomer section.
机译：集成式模块化水反应堆（IMR）是先进的小型反应堆之一。其集热器的主要冷却系统采用轻水冷却剂的两相流自然循环和内置式蒸汽发生器，该主要冷却系统被称为混合传热系统（HHTS），消除了竞争性经济并提高了安全性大直径管道，泵和增压器。蒸汽发生器有两种；一种是蒸汽发生器。一个（SGV）位于反应堆容器的蒸汽区域中以冷凝蒸气并控制一次系统压力，另一个（SGL）浸入两相混合物区域中以从混合物中除去热量并控制堆芯入口温度降至过冷状态。 SGV和SGL总共从核心中提取了1000MW的火电。两相向上流动中平均空隙率的设计目标约为20％至25％，与气泡流相对应.HHTS的性能受循环中气泡行为和空隙分布的影响。本研究通过商业代码α-FLOW的分析来研究上升下降部分的气泡行为。还估算了两相流中的自由表面蒸气分离，这对于确定SGV和SGL的所需容量很重要，并且还对具有小口径管道回路功能的蒸汽-水模拟测试中的蒸气分离进行了研究，以阐明其主要影响因素。这些准备。分析表明，两相流分布取决于上升管入口处的给定条件，这对应于堆芯燃尽。分析结果估计，在没有内部结构的情况下，以16GWd / t循环燃烧时，大约有30％的生成蒸气会分离到蒸气区域，而蒸汽-水模拟测试数据由感应速度参数排列，这建议了蒸气分离的主要因素是水平流向降液管段的系统压力和液体速度。

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