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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。
In order to study the behavior and system performance of each major equipment in the passive cooling system of the advanced water reactor, the China National Nuclear Power Research Institute has built a passive reactor based on the experimental device of the water supplement performance of the AC-600 full-pressure reactor Core emergency cooling system test device.A series of tests were conducted on the pilot device according to the different cold end breakout diameters, different pressure balance pipes and different automatic pressure relief system operating logic. The test results show that different tests Under the conditions, the passive core emergency cooling system can cool the core.