【摘要】 为了研究先进水堆非能动堆芯应急冷却系统中各主要设备的行为和系统性能,中国核动力研究设计院在AC-600全压堆芯补水箱补水性能实验装置的基础上建成了非能动堆芯应急冷却系统试验装置.在该试验货装置上,根据不同的冷端破口直径、不同的压力平衡管和不同的自动卸压系统操作逻辑进行了一系列试验,试验结果表明,不同的试验条件下,非能动堆芯应急冷却系统能够对堆芯进行冷却。更多还原

【Abstract】 For researching the main equipment and system of passive core emergency cooling system in advanced PWR, Nuclear Power Institute of China has built the passive core emergency cooling system facility on the base of AC600 core makeup tank facility, by adding some components. A series of experiments were conducted in the facility, simulating transients initiated by different size cold leg breaks, different pressure balance lines and different Automatic Depressurization System(ADS) actuation logic. These experiments indicated the adequate core cooling performance of the Passive Core Emergency Cooling System.更多还原