Abstract: Method and apparatus for assisting the loading of a reactor core with new and/or irradiated elongated fuel assemblies which includes inserting a fuel assembly with a fuel assembly carrier from a storage pit into a grid position of a reactor core with a refueling machine having propelling equipment, supplying an actual position of the fuel assembly carrier to the propelling equipment of the refueling machine during movement of the refueling machine between the storage pit and the reactor vessel, comparing the actual position of the fuel assembly carrier with a desired position of the fuel assembly carrier to find a deviation, and carrying out a correction of the deviation in the travelling movement of the refueling machine based upon the comparison.

Abstract: A method of determining with improved accuracy, the temperature margin to saturation of a heated pressurized liquid or vapor contained in a closed system. This method is characterized by the utilization of a direct measurement of the pressure margin to saturation instead of a measurement of the actual pressure of the system. The actual temperature of the system is used to determine the appropriate portion of the saturation curve to be used for the conversion of the pressure margin to saturation to the temperature margin to saturation.

Abstract: To control leaks between the primary and secondary circuits of a pressurized water reactor system, a pressure equalization is brought about by shutting off the live steam line and the feedwater line connected to the secondary circuit of the steam generator and by increasing the pressure prevailing in the resulting isolated secondary circuit by the injection of gas.

Abstract: In a device for the determination of the vibrations occurring at the internals of a reactor pressure vessel, it is possible to perform the maintenance of the vibration detector located in a housing from outside the reactor pressure vessel. One end of a guide tube is fed through a pipe stub to a receptacle cone connected to the core internals. The end of the guide tube facing away from the reactor pressure vessel is cup-shaped and is sealed with a cover. A flexible rod is connected to the housing and its other end extends into the cup-shaped end of the guide tube. The flexible rod and with it the housing connected to it can be inserted into the receptacle cone, providing good transmission of the vibrations prevailing at the internals, which reach an evaluation unit through the cable.