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A methodology for evaluating the probability of baffle-former bolt cracking was developed for applicability to presurized water reactors.
A database of SCC growth rates in commercial austenitic stainless steels exposed to pressurized water reactor (PWR) primary water environments was developed and analyzed from international data in high temperature water, with an emphasis on deaerated or hydrogenated water while also including water containing oxygen. Crack growth rate (CGR) disposition equations were derived to reflect the effects of stress intensity factor (K), temperature, Vickers hardness (HV, to represent retained deformation), with enhancement factors for oxygen-containing, high corrosion potential conditions. The tolerance to chloride and sulfate impurities in PWR primary water was also evaluated.
The formation of carbon deposits and fouling of tubes is one of the most common operational issues regarding the operability and lifetime of materials at an industrial scale. Several billion dollars are spent worldwide on annual basis to upgrade/change materials apart from revenue loss on account of production halt and additional costs incurred in maintenances. Particularly, the carbon deposition in the refining process is an evitable and undesired factor.
Traditional solutions for the chemical passivation of stainless steel are nitric acid based, with the addition of sodium dichromate as an inhibitor for precipitation hardened and free machining stainless steels. These passivation chemistries are difficult to handle from an environmental health and safety point of view, particularly the dichromate inhibited versions. Citric acid passivation has been pursued as a replacement for both nitric acid and inhibited nitric acid based chemistries for many years, and has been incorporated into consensus specifications such as ASTM A967 and SAE AMS2700.
Irradiation assisted stress corrosion cracking (IASCC) continues to be a major concern for thestructural integrity of core internals in both pressurized water reactors (PWRs) and boiling waterreactor (BWRs). While factors such as stress, an irradiated microstructure and a high temperaturewater environment are required for IASCC, a better understanding of the underlying mechanismhas become a subject of intense long-term research. In the last two decades, much progress hasbeen made in understanding IASCC susceptibility, though a clear cause-and-effect has yet to beestablished on the mechanism of intergranular cracking in highly neutron irradiated stainless steelsin the PWR environment.
Methods to protect austenitic stainless steel from polythionic acid stress corrosion cracking (SCC) found to occur during downtimes and contiguous shutdown and start-up periods. Historical Document 1986
Methods to protect austenitic stainless steel and other austenitic alloys from polythionic acid stress corrosion cracking (SCC) occurring during downtimes and contiguous shutdown and start-up periods. Historical Document 1993
Technical and quality assurance guidelines for the fabrication, welding, and installation of stainless chromium-nickel steel and nickel-alloy roll-bonded and explosion-bonded clad plate in air pollution control and other process equipment. Historical Document 1999
Technical and quality assurance guidelines for the fabrication, welding, and installation of stainless chromium-nickel steel and nickel-alloy roll-bonded and explosion-bonded clad plate in air pollution control & other process equipment. Historical Document 2004