Abstract: A cable-driven arm-reciprocating system particularly useful for transferring nuclear fuel bundles from a nuclear reactor pool to a spent fuel storage pool, wherein an arm-retracting cable extends from a winch drum around fixed and movable-axis sheaves to a retracting anchor device and an arm-extending cable extends from the same winch drum also around fixed and movable-axis sheaves to an extending anchor device, each anchor device including spring means for maintaining and allowing for variations in cable tension.

Abstract: A sodium-cooled fast reactor comprises at least one auxiliary heat exchanger constituted by a plurality of vertical heat-exchange modules each provided with a coolant circuit. A vertical cylindrical passage for each auxiliary heat exchanger extends through the reactor vault roof. The passage diameter is larger than the diameter of a heat-exchange module but smaller than the overall dimension of the auxiliary heat exchanger in horizontal cross-section. Each passage is closed by a shield plug after the modules have been placed in position, the modules being disposed around an axial extension of each shield plug.