By Damien Feron, Roger W Staehle
Stress Corrosion Cracking of Nickel dependent Alloys in Water-Cooled Nuclear Reactors: The Coriou impact presents the most recent info on brittle failure of metals in corrosive chemical environments lower than the effect of tensile stresses.
Nickel alloys are extra immune to SCC in addition to excessive temperatures and feature been generic in additional difficult environments reminiscent of nuclear energy vegetation. even if, those alloys can endure SCC below convinced stipulations, leading to part failure. A key determine in knowing the mechanisms of SCC in nickel alloys in water-cooled nuclear reactors is Henri Coriou of the CEA, France’s prime heart for nuclear study. This booklet assesses his paintings within the context of the most recent study on SCC in nickel alloys in nuclear energy plants.
- Up-to-date studies of modern learn findings from best specialists within the box
- Authoritative and comprehensively reviewed by means of the operating get together four on Nuclear Corrosion
- Showcases the wonderful caliber and technical accomplishments of Henri Coriou and CEA
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Additional info for Stress Corrosion Cracking of Nickel Based Alloys in Water-Cooled Nuclear Reactors: The Coriou Effect
E) Destructive examination of one nozzle from Flamanville-2, showing X-ray diffraction measurements of inner surface residual stresses. ID, inner diameter; OD, outer diameter. 1 Fermi and the pile Atomic energy was born with Enrico Fermi’s pile on December 7, 1942, when a chain reaction was ﬁrst observed. 35 A sequential failure occurred on the reactor vessel head of the Davis Besse pressurized water reactor in 2002. (a) First, stress corrosion cracking (SCC) occurred in a control rod drive housing fabricated from Alloy 600, which was fully perforated, as shown in (b).
Coriou’s work was of the same ilk. Coriou seemed presciently linked to Rickover’s personal commitment to high-quality work in the ﬁeld of nuclear power. 4. For Coriou to have chosen to study high-Ni alloys is consistent with his insights. Even by 1953 stainless steels had sustained SCC in the heat exchangers of S1Wg steam generators. It was clear at this time that some new class of alloys was needed for pure-water environments, and investigation of the high-nickel alloys, including Alloy 600, seemed appropriate.
The Corrosion and Wear Handbook was intended to provide the substance of relevant corrosion from contemporary information; in some ways, however, it failed in its mission, to the detriment of corrosion testing and analysis. For example, it lacked any consideration of superheated crevices on the secondary side, which was where SCC in the Naval applications was actually occurring. g “S1W” is the designation to the ﬁrst water-cooled submarine reactor. The S1W was the reactor used in the prototype of the Nautilus submarine and was operated at the Idaho site.