本文介绍了在莫尔核能研究中心进行的快堆安全实验。实验工作在堆内钠回路中进行。被试验的快堆元件棒束在堆内辐照。在组件中有一个堵塞装置。人为地切断堵塞装置中的冷却流量而引起钠沸腾和元件熔化事故。试验表明,由于堆芯流道堵塞而引起元件损坏事故蔓延的可能性可以排除。 This article describes the fast reactor safety experiments conducted at the Moore Institute of Nuclear Energy. Experimental work in the heap sodium loop. The bundles of fast reactors that were tested were irradiated within the stack. There is a jam in the assembly. Artificially cut off the cooling flow in the clogging device caused sodium boiling and component melting accident. Tests show that the possibility of component damage due to blockage of the core runner can be ruled out.