By Damien Feron, Roger W Staehle
Stress Corrosion Cracking of Nickel dependent Alloys in Water-Cooled Nuclear Reactors: The Coriou influence presents the newest details on brittle failure of metals in corrosive chemical environments less than the effect of tensile stresses.
Nickel alloys are extra immune to SCC in addition to excessive temperatures and feature been common in additional hard environments reminiscent of nuclear energy crops. although, those alloys can endure SCC below convinced stipulations, leading to part failure. A key determine in realizing the mechanisms of SCC in nickel alloys in water-cooled nuclear reactors is Henri Coriou of the CEA, France’s major middle for nuclear learn. This booklet assesses his paintings within the context of the most recent examine on SCC in nickel alloys in nuclear energy plants.
- Up-to-date reports of modern learn findings from best specialists within the box
- Authoritative and comprehensively reviewed by means of the operating celebration 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
86. From the point of view of SCC, the calculable stresses are only those from pressure, thermal, and bending sources. Nonetheless, residual stresses from fabrication are sufﬁcient to produce SCC. Further, at the top of tube sheet (TTS), the carbon steel corrodes Historical views on stress corrosion cracking of nickel-based alloys: the Coriou effect 31 (a) Freespan Tube support plate Fe3O4 G – (b) Primary water, TP (c) Tube Wall Superheated surfaceTH – TC Steam – Cl (Cl , HCl) SOx SiOx (SiO2, complex compounds) AlOx (S6+ S4+ S2+ S0+ S2–) (AL2O3, complex compounds) including retrograde compounds.
65) b. On the free span, SCC (when it does occur) is on the secondary side and is a result of a combination of scratches and residual stresses due to fabrication. c. At the TTS on the secondary side, the stresses are mainly caused by the plastic deformation from expansion of the tube as well as some contribution from tube fabrication stresses. W. R. 32 (a) Fraction of (RT) yield stress (YS) versus time to failure for mill-annealed Alloy 600 (Alloy 600MA) at 365 C in pure water. Yield point stresses are in the range of 323e386 MPa.
20 Gradient of plastic strain at the surface of stainless steel. Courtesy of Peter Andresen. 21 Stress corrosion cracking at the interface between a weld and matrix material. Courtesy of Peter Andresen. or inside crevices or deposits, much like what has occurred in vertical commercial steam generators over the later period from 1960 through the 1990s. This secondary-side corrosion was associated with superheated crevices where chemicals could concentrate. Signiﬁcant local superheat exists at two locations on the secondary side: the outer diameter of tubes adjacent to tube support (TSP) and outside the tube wall at the top of the tubesheet.
Stress Corrosion Cracking of Nickel Based Alloys in Water-cooled Nuclear Reactors. The Coriou Effect by Damien Feron, Roger W Staehle