Home / Publications / Journals / Nuclear Technology / Volume 46 / Number 3
Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 582-590
Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32369
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An Electricité de France survey on the behavior of cracked tubes under operating conditions of an industrial steam generator was conducted. A comparison was first made of the development kinetics of the cracks according to the type of material: Incoloy 800, Cr—1 Mo, 9 Cr—2 Mo, and to the initial leak. Then, two successive stages are evidenced in the self-development process of a water leak into sodium: