首页> 外文会议>ASME(American Society of Mechanical Engineers)/JSME(Japanese Society of Mechanical Engineers) Thermal Engineering Summer Heat Transfer Conference 2007 >EXPERIMENTS AND ANALYTICAL SIMULATION WORK ON AN INNOVATIVE STEAM-INJECTOR-DRIVEN PASSIVE CORE INJECTION COOLING SYSTEM
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EXPERIMENTS AND ANALYTICAL SIMULATION WORK ON AN INNOVATIVE STEAM-INJECTOR-DRIVEN PASSIVE CORE INJECTION COOLING SYSTEM

机译:蒸汽喷射驱动的被动式核心注射冷却系统的实验与分析模拟

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A Steam Injector (SI) is a simple, compact, passive pump which also functions as a high-performance direct-contact compact heater. We are developing this innovative concept by applying the SI system to core injection systems in Emergency Core Cooling Systems (ECCS) to further improve the safety of nuclear power plants. Passive ECCS in nuclear power plants would be inherently very safe and would prevent serious accidents by keeping the core covered with water (Severe Accident-Free Concept). The Passive Core Coolant Injection System driven by a high-efficiency SI is one that, in an accident such as a loss of coolant accident (LOCA), attains a higher discharge pressure than the supply steam pressure used to inject water into the reactor by operating the SI using water stored in the pool as the water supply source and steam contained in the reactor as the source of pressurization energy. The passive SI equipment would replace large, rotating machines such as pumps and motors, so eliminating the possibility of such equipment failing. In this Si-driven Passive Core Coolant Injection System (SI-PCIS), redundancy will be provided to ensure that the water and steam supply valves to the SI open reliably, and when the valves open, the SI will automatically start to inject water into the core to keep the core covered with water. The SI used in SI-PCIS works for a range of steam pressure conditions, from atmosphere pressure through to high pressures, as confirmed by analytical simulations which were done based on comprehensive experimental data obtained using reduced scale SI. We did further simulations and evaluations of the core cooling and coolant injection performance of SI-PCIS in BWR using RETRAN-3D code, developed using EPRI and other utilities, for the case of small LOCA. Reactors equipped with passive safety systems - the gravity-driven core cooling/injection system (GDCS) and depressurization Valves (DPV) - would inevitably end up having large LOCA, even if they are initially small LOCA, as depressurization valves are forcibly opened in order to inject coolant from the GDCS pool to the GDCS water head at up to ~0.2MPa. On the other hand, our simulation demonstrated that SI-PCIS could prevent large LOCA occurring in reactors by having by coolant discharged into the core in the event of small LOCA or when DPV unexpectedly open.
机译:蒸汽喷射器(SI)是一种简单,紧凑的无源泵,还可以用作高性能的直接接触式紧凑型加热器。我们正在通过将SI系统应用于紧急堆芯冷却系统(ECCS)的堆芯喷射系统中来开发这种创新概念,以进一步提高核电厂的安全性。核电厂中的被动ECCS本质上是非常安全的,并且通过使堆芯充满水,可以防止发生严重事故(无严重事故概念)。由高效率SI驱动的被动堆芯冷却液注入系统是一种在发生事故(例如冷却剂损失事故(LOCA))时,获得比用于通过将水注入反应堆的供应蒸汽压力更高的排放压力的系统。 SI使用池中存储的水作为供水源,而反应器中包含的蒸汽作为加压能量源。无源SI设备将替代大型旋转电机,例如泵和电机,因此消除了此类设备发生故障的可能性。在此由硅驱动的被动堆芯冷却剂注入系统(SI-PCIS)中,将提供冗余以确保SI的供水和蒸汽供应阀可靠地打开,并且当这些阀打开时,SI会自动开始向其中注入水。核心要保持核心被水覆盖。 SI-PCIS中使用的SI适用于从大气压到高压的各种蒸汽压力条件,这是通过分析模拟所证实的,分析模拟是基于使用缩小比例SI获得的综合实验数据完成的。对于小型LOCA,我们使用EPRI和其他实用程序开发的RETRAN-3D代码对BWR中的SI-PCIS堆芯冷却和冷却剂注入性能进行了进一步的仿真和评估。配备无源安全系统的反应堆-重力驱动堆芯冷却/喷射系统(GDCS)和减压阀(DPV)-最终将不可避免地具有较大的LOCA,即使它们最初是较小的LOCA,因为按顺序强制打开减压阀从GDCS池向GDCS水头注入冷却剂,最高可达〜0.2MPa。另一方面,我们的仿真表明,SI-PCIS可以通过在LOCA较小或DPV意外打开时将冷却剂排放到堆芯中来防止反应堆中出现较大的LOCA。

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