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Large Scale BWR Containment LOCA Response Test at the INKA Test Facility

机译:在INKA测试设施进行的大规模BWR围堵LOCA响应测试

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KERENA is an innovative boiling water reactor concept with passive safety systems (Generation Ⅲ+) of AREVA. The reactor is an evolutionary design of operating BWRs (Generation Ⅱ). In order to verify the functionality and performance of the KERENA safety concept required for the transient and accident management, the test facility "Integral Teststand Karlstein" (INKA) was built in Karlstein (Germany). It is a mock-up of the KERENA boiling water reactor containment, with integrated pressure suppression system. The complete chain of passive safety components is available. The passive components and the levels are represented in full scale. Only one of the four passive trains of KERENA is installed in the INKA test facility. The volume scaling of the containment compartments is approximately 1:24. This results in an effective volume scaling related to the passive systems of 1:6. The reactor pressure vessel (RPV) is simulated via the steam accumulator vessel of the Karlstein Large Valve Test Facility. This vessel provides an energy storage capacity of approximately 1/6 of the KERENA RPV and is supplied by a Benson boiler with a thermal power of 22 MW. With respect to the available power supply, the containment- and system-sizing the facility is one of the largest test facilities for passive integral system testing ever operated. From 2009 to 2012, single component tests of the passive systems Emergency Condenser, Containment Cooling Condenser, Core Flooding System were conducted. On March 21st, 2013, the first large-scale only passively managed integral accident test of a boiling water reactor was simulated at INKA. The integral test measured the combined response of the KERENA passive safety systems to the postulated initiating event: "Main Steam Line Break" (MSLB) inside the Containment with decay heat simulation. The decay heat was simulated by simultaneous steam introduction and liquid water removal from the pressure vessel. The results of the performed integral test (MSLB) showed that the passive safety systems alone are capable to bring the plant to stable conditions meeting all required safety targets with sufficient margins. Therefore the test verified the function of those components and the interplay between them as response to an anticipated accident scenario. The test provided evidence that the INKA test facility is capable to perform integral system verification tests of passive safety concepts under plant-relevant scaling and plant-like thermodynamic conditions, including the feedback of the accident to the pressure vessel. Being equipped with a state of the art pressure suppression containment INKA is capable to perform also containment response tests for Generation Ⅱ BWRs. Those test results could be used to validate containment response calculation for various LOCA and non- LOCA scenarios. The test could tackle the heat intake and temperature distribution that establishes in the gas and water volume of multi compartment containment or the re-distribution/relocation of non- condensable gases depending on the momentum of the LOCA coolant jet introduced into the containment.
机译:KERENA是具有AREVA被动安全系统(第Ⅲ+代)的创新沸水反应堆概念。该反应堆是运行中的BWR(第二代)的进化设计。为了验证瞬态和事故管理所需的KERENA安全概念的功能和性能,在卡尔施泰因(德国)建造了“ Integral Teststand Karlstein”(INKA)测试设施。它是KERENA沸腾反应堆安全壳的模型,带有集成的压力抑制系统。可提供完整的被动安全组件链。无源组件和电平以完整比例表示。在INKA测试设备中,仅安装了KERENA的四列被动列车中的一列。密闭隔室的体积比例约为1:24。这导致与1:6的被动系统相关的有效体积缩放。反应堆压力容器(RPV)通过Karlstein大阀门测试设施的蒸汽储罐进行模拟。该容器的储能能力约为KERENA RPV的1/6,由Benson锅炉提供,功率为22 MW。关于可用电源,安全壳和系统规模的设施是有史以来进行的无源集成系统测试的最大测试设施之一。从2009年到2012年,对被动系统应急冷凝器,安全壳冷却冷凝器,堆芯注水系统进行了单组件测试。 2013年3月21日,INKA进行了沸水反应堆的首次大规模,仅被动管理的整体事故整体测试。整体测试通过衰减热模拟测量了KERENA被动安全系统对假定的发起事件:安全壳内部的“主蒸汽管线断裂”(MSLB)的综合响应。通过同时引入蒸汽和从压力容器中除去液态水来模拟衰变热。进行的整体测试(MSLB)的结果表明,仅被动安全系统就能够使工厂达到稳定的条件,并以足够的余量满足所有要求的安全目标。因此,该测试验证了这些组件的功能以及它们之间的相互作用,以响应预期的事故情况。该测试提供了证据,表明INKA测试设备能够在与工厂相关的缩放比例和类似于工厂的热力学条件下,包括对事故向压力容器的反馈中,对被动安全概念进行完整的系统验证测试。配备了最先进的压力抑制容器INKA还能对Ⅱ代BWR执行容器响应测试。这些测试结果可用于验证各种LOCA和非LOCA方案的安全壳响应计算。该测试可以解决在多隔间安全壳的气体和水体积中建立的吸热和温度分布,或者根据引入安全壳的LOCA冷却剂射流的动量来解决非冷凝性气体的重新分布/重新布置。

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