首页> 外文会议>ASME International Mechanical Engineering Congress and Exposition >INTEGRAL EFFECT TEST ON OPERATIONAL PERFORMANCE OF THE PAFS (PASSIVE AUXILIARY FEEDWATER SYSTEM) FOR A SGTR (STEAM GENERATOR TUBE RUPTURE) ACCIDENT
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INTEGRAL EFFECT TEST ON OPERATIONAL PERFORMANCE OF THE PAFS (PASSIVE AUXILIARY FEEDWATER SYSTEM) FOR A SGTR (STEAM GENERATOR TUBE RUPTURE) ACCIDENT

机译:用于SGTR(蒸汽发生器管破裂)事故PAFS(被动辅助给水系统)的操作性能的积分效果试验

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The PAFS is one of the advanced safety features adopted in the APR+ (Advanced Power Reactor Plus) which is intended to completely replace a conventional active auxiliary feedwater system. The PAFS cools down the steam generator secondary side and eventually removes the decay heat from the reactor core by adopting a natural convection mechanism; i.e., condensing steam in nearly-horizontal U-tubes submerged inside the PCCT (Passive Condensation Cooling Tank). With an aim of verifying the operational performance of the PAFS, the experimental program of an integral effect test is in progress at KAERI (Korea Atomic Energy Research Institute). The test facility, ATLAS-PAFS was constructed to experimentally investigate the thermal hydraulic behavior in the primary and secondary systems of the APR+ during a transient when the PAFS is actuated. Since the ATLAS-PAFS facility simulates a single train of the PAFS, the anticipated accident scenarios in the experiment include FLB (Feedwater Line Break), MSLB (Main Steam Line Break), and SGTR (Steam Generator Tube Rupture). Among them, SGTR was considered as one of the design basis accidents having a significant impact on safety in a viewpoint of radiological release. Therefore, the SGTR test was determined to be the integral effect test item in the frame of the ATLAS-PAFS experimental program. In this study, the PAFS-SGTR-HL-02 test was performed to simulate a double-ended rupture of a single U-tube in the hot side of the steam generator of the APR+. The three-level scaling methodology was taken into account to determine the test conditions of the steady-state and the transient. The pressures and temperatures of the system and the data related to the PAFS operation were collected with the measurement of the break flow. The initial steady-state conditions and the sequence of event of SGTR scenario for the APR+ were successfully simulated with the ATLAS-PAFS facility. And it was shown that the pressure and the temperature of the primary system were continuously decreased during the heat removal by the PAFS operation. The water pool in the PCCT was heated up to the saturation condition and the evaporation of the water made a decrease of the PCCT water level. It could be concluded from the present experimental result that the APR+ has the capability of coping with the hypothetical SGTR scenario with adopting the PAFS and the proper set-points of its operation.
机译:的PAFS是在其旨在完全替代传统的活性辅助给水系统中的APR +(高级电源反应堆加)功能采用了先进的安全的一个。所述PAFS冷却蒸汽发生器二次侧,并最终通过采用自然对流机制去除从反应堆堆芯衰变热;即,在PCCT内部浸没在PCCT(无源冷凝冷却罐)内的几乎水平U形管中的冷凝蒸汽。随着验证PAFS的运营绩效的目标,是整体效果测试的实验方案是在KAERI(韩国原子能研究所)的进展。测试设备,ATLAS-PAFS构建为实验调查一个瞬变期间在APR +的初级和次级系统中的热液压行为当PAFS被致动。由于ATLAS-PAFS设施模拟PAFS单列车,在实验中预期的事故场景包括FLB(给水换行符),MSLB(主蒸汽管破裂),和SGTR(蒸汽发生器管道破裂)。其中,SGTR被视为具有放射性中释放的观点对安全有显著影响,设计基准事故之一。因此,SGTR测试被确定为在ATLAS-PAFS实验方案的帧的积分效应测试项目。在这项研究中,进行了PAFS-SGTR-HL-02测试,以模拟单个U形管的一个双端破裂在APR +的蒸汽发生器的热侧。三级缩放方法被考虑来确定稳态和瞬态的测试条件。的压力和系统的温度和相关的PAFS操作的数据与破流量的测量收集。初始稳定状态和SGTR情景的事件为APR +的顺序进行了成功的模拟与ATLAS-PAFS设施。且显示了压力和初级系统的温度的热去除由PAFS操作期间连续降低。在PCCT水池加热到饱和条件和水的蒸发作出的PCCT水位的下降。它可以从目前的实验结果是APR +具有与采用PAFS和正确的操作设定点的假设情景SGTR应对的能力,可以得出结论。

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