Please use this identifier to cite or link to this item:
|Title:||Stress Corrosion Cracking Testing in SCW - Results of SSRT Tests|
|Authors:||NOVOTNY Radek; HAEHNER Peter; JANIK PREMYSL; SIEGL J; HAUSILD P; RIPPLINGER Stefan|
|Citation:||Proceedings of the 5th International Symposium on Supercritical Water-Cooled Reactors p. P32 (1-16)|
|Publisher:||Canadian Nuclear Society|
|Type:||Articles in periodicals and books|
|Abstract:||The presented paper summarizes the results of stress corrosion cracking (SCC) susceptibility tests in supercritical water (SCW), studied for austenitic alloys 316L, 316NG, 347HP and Alloy 690 with the aim to identify maximum SCW temperature usability and specific failure mechanisms prevailing during slow strain-rate tensile (SSRT) tests in ultra-pure demineralized SCW solution with controlled oxygen content. Besides the strain rate (resp. crosshead speed), the oxygen content was varied in the series of tests in case of austenitic stainless steel 316L. The fractography confirmed that failure was due to a combination of transgranular SCC and transgranular ductile fracture. Based on fractographic findings a phenomenological map describing the SCC regime of SSRT test parameters could be proposed for AISI 316L.|
|JRC Directorate:||Energy, Transport and Climate|
Files in This Item:
There are no files associated with this item.
Items in repository are protected by copyright, with all rights reserved, unless otherwise indicated.