Patent Number: 041486862
Section: description

DETAILED DESCRIPTION The heat exchanger module, which can be grouped in parallel with other modules, includes a jacket or outer casing 1 having a generally cylindrical shape, inside which is disposed a coaxial inner casing 2 surrounding a nest of tubes 3, comprising a large number of parallel tubes, not shown. The nest of tubes 3 is connected to a lower tubular plate 4 and to an upper tubular plate 5, the tubes forming at their top part an expansion-bend 6. The nest of tubes is intended to convey the flow of water which is to be heated to superheated steam. The water is admitted at the bottom part of the module through tubing 7 and is discharged in the state of superheated steam at the upper part through tubing 8. An annular space 9 disposed in the upper part of the module between the casings 1 and 2 is connected to inlet tubing 10 for liquid sodium heated in a rapid neutron nuclear reactor. During normal operation, the liquid sodium rises between the casings 1 and 2, then flows into the casing 2 around the tubes of the nest 3, in opposition to the flow of the water which is to be vaporized and superheated. An annular space 11 disposed in the lower part of the module between the casings 1 and 2 is connected to tubing 12 for discharging the liquid sodium cooled in the exchanger. The casing 1 of the module is surrounded over its entire height between the annular inlet space 9 and the outlet space 10 with a coaxial outer casing or jacket 13 defining an annular space 14 with casing 2. This space 14 is connected to an ambient air inlet tube 15 and an ambient air outlet tube 16. A blower 17 ensures the circulation of air in the annular space 14. Horizontal spikes 18 are provided over the entire height of the outer surface of the casing 1 that is under the jacket 13. The spikes 18 serve to improve the heat exchange coefficient between the liquid sodium and the air blown through the space 14 when the nuclear reactor is shut down. When a rapid neutron nuclear reactor is shut down, the power which it supplies does not die away immediately, but decreases gradually. As the flow of water must be stopped on shut down, the residual power must be dissipated elsewhere until its supply has died away. This dissipation is effected by heat exchange between the sodium and the air flowing in the annular space 14 in the direction shown by arrows 19, 20. However, as the heat exchange coefficient of air is relatively low, it is improved by the use of the spikes 18 so as to ensure the dissipation of the residual heat with a moderate air flow. The spikes 18 are immersed in the air flow and may have a height which is of the order of half the width of the annular space 14. These spikes 18 could be replaced by other auxiliary heat exchange means, such as vertical fins. When the residual power generated by the nuclear reactor has greatly decreased, it is possible to stop the air blower as the natural air flow by convection becomes sufficient to dissipate the remaining fraction of residual power. If the water/sodium heat exchanger is composed of several modules grouped together in parallel, it is preferable to provide only one blower feeding air to the coverings of the various modules through appropriate tubes. Although the structure of the heat exchange module which has just been described appears to be preferable, it will be understood that various modifications can be made thereto without going beyond the scope of the invention, it being possible to replace particular elements described by others which fulfill the same technical function.