Maintenance and repair of LMFBR steam generators. III. R and D work on maintenance and repair

In the case of SPX 1, the research and development work has concerned the replacement of rupture disks, the plugging of the tubes and a certain number of facilities including hydrogen detection, detection of wastage defects on the exchange tubes and visualization of the tubes from the exterior. The final restatement of the specific SPX I equipment will be completed during the power plant commissioning tests. Then, all the real conditions for the application of these components will be presented. Work is now going on within the framework of the reactor system, in particular for SPX 2. In this framework, there are two main lines of research related respectively to the means of water leak detection in sodium and the inspection arrangements that will be used either periodically, or following a sodium water reaction