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Title: In-service monitoring and servicing after leak detection for the liquid-metal fast breeder reactor steam generators of Phenix and Super Phenix

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:5933998

Mandatory safety-related design requirements include the absolute leak-tightness of the heat exchange surfaces separating sodium from water and the prevention of violent sodium-water reactions. After briefly recalling the various leak situations likely, and consequences (wastage and secondary ruptures), the precautions taken during steam generator (SG) designing, manufacturing, and operating phases to minimize leak hazards and satisfy the mechanical design basis requirements adopted for secondary loop components are analyzed. The in-service monitoring systems provided (hydrogen detection, acoustic detection) and the means devised to keep leak consequence within acceptable limits (rupture disks) are described. The actions initiated by signals from these systems are reviewed (reactor shutdown, SG isolation pressure-relief, cooling and inertization of sodium or water-steam circuits). Plant overhaul procedures, servicing operations on the SG itself (whipping tube localization, damage assessment on adjoining tubes by insertion of an eddy-current probe, removal of damaged tubes) and on the secondary loop after detection and prior to restartup are presented. For each device and situation mentioned, a comparison is drawn, underlining the fundamental differences existing in the different types of SGs and tube materials.

Research Organization:
20, Avenue Edouard-Herriot, 92350 Le Plessis-Robinson
OSTI ID:
5933998
Journal Information:
Nucl. Technol.; (United States), Vol. 58:2
Country of Publication:
United States
Language:
English