Safety apparatus for a nuclear reactor comprising an absorbing element having a supporting head connected by a disconnectable linkage constituted by the armature of an electromagnet to the end of an axially movable vertical operating rod, said linkage being such that in the case of a disconnection the absorbing element slides by gravity in a passage bounded by an open container through the core of the reactor, wherein the operating rod is associated with a metal member having an expansion coefficient which is significantly higher than that of the armature of the electromagnet, whereby in the case of a temperature rise a separating force is exerted between the head of the absorbing element and the operating rod.
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