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PANDA TESTS FOR INNOVATIVE PLANTS WITH PASSIVE SAFETY SYSTEMS

机译:Panda测试有源安全系统的创新植物

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A new test series is being planned for the PANDA facility to experimentally investigate the containment loss-of-coolant accident (LOCA) response of innovative nuclear power plants with passive safety systems. PANDA is a thermal-hydraulic containment test facility located at the Paul Scherrer Institut (PSI) in Switzerland. The modular representation of the containment in PANDA gives flexibility to investigate a variety of different passive decay heat removal systems for the next generation of Light Water Reactors (LWR). Modularity and a large scale allow examination of the effects of non-uniform spatial distribution of steam and non-condensable gas in the system. The recently completed test series focused on the longterm response and performance of the passive containment cooling system of the Simplified Boiling Water Reactor (SBWR). One of the planned PANDA test series will utilize the European Simplified Boiling Water Reactor (ESBWR) configuration to study several new features introduced in the more advanced containment design of this plant. A major design change (with respect to the SBWR) is related to the passive emergency core cooling system. The gas space above the water pool of this Gravity Driven Cooling System (GDCS) is now connected to the wetwell gas space rather than the drywell. As a consequence, the wetwell gas space volume increases during the GDCS injection phase as water drains from the pool to the reactor pressure vessel. This provides an additional pressure margin under hypothetical accident scenarios and allows for a compact containment design. The effect on containment response due to the time-dependent change in wetwell gas space volume will be investigated for different LOCA scenarios. A series of eight transient system tests is planned. The new PANDA test series will provide an extensive data base, which will contribute to containment design of innovative passive plants, system code assessment and analysis of particular phenomena.
机译:计划为熊猫设施计划进行新的测试系列,以实验研究创新核电站与被动安全系统的遏制冷却液事故(LOCA)响应。熊猫是位于瑞士的Paul Scherrer Institut(PSI)的热液压遏制测试设施。熊猫遏制的模块化表示可灵活地调查用于下一代轻水反应器(LWR)的各种不同的被动衰变除去系统。模块化和大规模允许检查系统中蒸汽和不可冷凝气体的不均匀空间分布的影响。最近完成的测试系列专注于简化沸水反应器(SBWR)的被动遏制冷却系统的长期响应和性能。其中一个计划的熊猫试验系列将利用欧洲简化的沸水反应堆(ESBWR)配置来研究该植物更先进的遏制设计中引入的几个新功能。主要的设计变更(关于SBWR)与被动紧急核心冷却系统有关。该重力驱动冷却系统(GDC)的水池上方的气体空间现在连接到湿度气体空间而不是干燥。因此,随着从池中的水排出到反应器压力容器,在GDCS注入阶段期间,湿阱气体空间量增加。这在假设事故方案下提供了额外的压力余量,并允许紧凑的容纳设计。对于不同的基因座情景,将研究由于依赖于韦维空气空间体积的时间依赖性变化导致的遏制响应的影响。计划了一系列八个瞬态系统测试。新的熊猫测试系列将提供一个广泛的数据库,这将有助于遏制创新的被动设备,系统代码评估和特定现象的分析。

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