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A PANDA integral test on the effect of light gas on a Passive Containment Cooling System (PCCS)

机译:PANDA积分试验,对轻气体对被动安全壳冷却系统(PCCS)的影响

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摘要

As part of the Euratom project TEMPEST (Testing and Enhanced Modelling of Passive Evolutionary Systems Technology for Containment Cooling), a series of five tests was performed in the PANDA facility to experimentally investigate the distribution of hydrogen inside the containment and its impact on the performance of the Passive Containment Cooling System (PCCS) designed for the Economic Simplified Boiling Water Reactor (ESBWR). In a postulated severe accident a large amount of hydrogen could be released in the Reactor Pressure Vessel (RPV) as a consequence of the cladding Metal-Water (M-W) reaction and discharged together with steam to the Drywell (DW) compartment The retention of hydrogen in the DW, instead to be vented in the Wetwell (WW), has a positive effect toward the mitigation of the system pressure build-up. Hydrogen retention in the DW is a consequence of the stratification phenomena driven by the steam-hydrogen density difference. The paper presents the experimental results of the integral Test T1.2 performed in the PANDA facility. Helium was used to simulate hydrogen and the specific PANDA facility configuration included a dead-end volume, allowing for retaining a portion of the released helium in the DW compartment. The results from Test T1.2 showed that the containment end pressure is mainly determined by the redistribution of non-condensable gas inside the containment system and the temporary deterioration of the PCCS performance during the helium release phase plays a minor role.
机译:作为Euratom项目TEMPEST(用于安全壳冷却的无源进化系统技术的测试和增强模型)的一部分,在PANDA设施中进行了一系列的五个测试,以实验方式研究安全壳内氢的分布及其对氢性能的影响。为经济简化沸水反应堆(ESBWR)设计的被动安全壳冷却系统(PCCS)。在假定的严重事故中,由于金属-水(MW)的包层反应,反应堆压力容器(RPV)中可能释放大量氢气,并与蒸汽一起排入干井(DW)舱室。 DW中的水而不是排放到Wetwell(WW)中,对减轻系统压力的积聚具有积极作用。 DW中的氢气滞留是由蒸汽-氢气密度差驱动的分层现象的结果。本文介绍了在PANDA设施中执行的整体测试T1.2的实验结果。氦气用于模拟氢气,特定的PANDA设施配置包括死角容积,可以将一部分释放的氦气保留在DW隔室中。测试T1.2的结果表明,安全壳末端压力主要由安全壳系统内不可冷凝气体的重新分布决定,在氦气释放阶段PCCS性能的暂时下降起着很小的作用。

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  • 来源
    《Nuclear Engineering and Design》 |2011年第11期|p.4551-4561|共11页
  • 作者单位

    Paul Scherrer lnstitut (PSI), Nuclear Energy and Safety Research Department, Laboratory for Thermal-Hydraulics, 5232 Villigen PSI, Switzerland;

    Paul Scherrer lnstitut (PSI), Nuclear Energy and Safety Research Department, Laboratory for Thermal-Hydraulics, 5232 Villigen PSI, Switzerland;

    Paul Scherrer lnstitut (PSI), Nuclear Energy and Safety Research Department, Laboratory for Thermal-Hydraulics, 5232 Villigen PSI, Switzerland;

    Paul Scherrer lnstitut (PSI), Nuclear Energy and Safety Research Department, Laboratory for Thermal-Hydraulics, 5232 Villigen PSI, Switzerland;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
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