Download or read book IRRADIATION ASSISTED STRESS CORROSION CRACKING OF MODEL AUSTENITIC STAINLESS STEEL ALLOYS NUREG CR 6678 U S NUCLEAR REGULATORY COMMIS written by and published by . This book was released on 2001* with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book IRRADIATION ASSISTED STRESS CORROSION CRACKING OF MODEL AUSTENITIC STAINLESS STEELS IRRADIATED IN THE HALDEN REACTOR NUREG CR 5608 U S NUCLEAR REGULATORY Commission written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1999* with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Irradiation assisted Stress Corrosion Cracking of Model Austenitic Stainless Steel Alloys written by H. M. Chung and published by . This book was released on 2000 with total page 31 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Irradiation assisted Stress Corrosion Cracking of Model Austenitic Stainless Steels Irradiated in the Halden Reactor written by H. M. Chung and published by . This book was released on 1999 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Irradiation Assisted Stress Corrosion Cracking of Austenitic Stainless Steels and Alloy 690 from Halden Phase II Irradiations written by Y. Chen and published by . This book was released on 2008 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt: This work is an ongoing effort at Argonne National Laboratory on the mechanistic study of irradiation-assisted stress corrosion cracking (IASCC) in the core internals of light water reactors.
Download or read book Irradiation assisted Stress Corrosion Cracking Behavior of Austenitic Stainless Steels Applicable to LWR Core Internals written by H. M. Chung and published by . This book was released on 2006 with total page 91 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Irradiation assisted Stress Corrosion Cracking Behavior of Austenitic Stainless Steels Applicable to LWR Core Internals written by and published by . This book was released on 2006 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Irradiation assisted Stress Corrosion Cracking of Austenitic Stainless Steels in BWR Environments written by and published by . This book was released on 2010 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Irradiation assisted Stress Corrosion Cracking of Austenitic Stainless Steels in BWR Environments written by Y. Chen and published by . This book was released on 2010 with total page 89 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Irradiation assisted Stress Corrosion Cracking of Model Austenitic Stainless Steel written by and published by . This book was released on 1999 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Slow-strain-rate tensile (SSRT) tests were conducted on model austenitic stainless steel (SS) alloys that were irradiated at 289 C in He. After irradiation to (almost equal to)0.3 x 1021 n · cm2 and (almost equal to) 0.9 x 1021 n · cm−2 (E> 1 MeV), significant heat-to-heat variations in the degree of intergranular and transgranular stress corrosion cracking (IGSCC and TGSCC) were observed. At (almost equal to)0.3 x 1021 n · cm−2, a high-purity heat of Type 316L SS that contains a very low concentration of Si exhibited the highest susceptibility to IGSCC. In unirradiated state, Types 304 and 304L SS did not exhibit a systematic effect of Si content on alloy strength. However, at (almost equal to)0.3 x 1021 n · cm−2, yield and maximum strengths decreased significantly as Si content was increased to>0.9 wt.%. Among alloys that contain low concentrations of C and N, ductility and resistance to TGSCC and IGSCC were significantly greater for alloys with>0.9 wt.% Si than for alloys with 0.47 wt.% Si. Initial data at (almost equal to)0.9 x 1021 n · cm−2 were also consistent with the beneficial effect of high Si content. This indicates that to delay onset of and reduce susceptibility to irradiation-assisted stress corrosion cracking (IASCC), at least at low fluence levels, it is helpful to ensure a certain minimum concentration of Si. High concentrations of Cr were also beneficial; alloys that contain
Download or read book Fracture Toughness and Crack Growth Rates of Irradiated Austenitic Stainless Steels Nureg cr 6826 U s Nuclear Regulatory Commission written by and published by . This book was released on 2003* with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Stress Corrosion Cracking of Austenitic Stainless Steel written by McIntyre R. Louthan and published by . This book was released on 1964 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Sicherheitseigenschaften kleiner Heizrekatoren written by and published by . This book was released on 1987 with total page 3 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Deposits near Medicine Hat Alberta Canada written by and published by . This book was released on 1970 with total page 3927 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Cracking Behavior and Microstructure of Austenitic Stainless Steels and Alloy 690 Irradiated in BOR 60 Reactor Phase I written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Cracking behavior of stainless steels specimens irradiated in the BOR-60 at about 320 C is studied. The primary objective of this research is to improve the mechanistic understanding of irradiation-assisted stress corrosion cracking (IASCC) of core internal components under conditions relevant to pressurized water reactors. The current report covers several baseline tests in air, a comparison study in high-dissolved-oxygen environment, and TEM characterization of irradiation defect structure. Slow strain rate tensile (SSRT) tests were conducted in air and in high-dissolved-oxygen (DO) water with selected 5- and 10-dpa specimens. The results in high-DO water were compared with those from earlier tests with identical materials irradiated in the Halden reactor to a similar dose. The SSRT tests produced similar results among different materials irradiated in the Halden and BOR-60 reactors. However, the post-irradiation strength for the BOR-60 specimens was consistently lower than that of the corresponding Halden specimens. The elongation of the BOR-60 specimens was also greater than that of their Halden specimens. Intergranular cracking in high-DO water was consistent for most of the tested materials in the Halden and BOR-60 irradiations. Nonetheless, the BOR-60 irradiation was somewhat less effective in stimulating IG fracture among the tested materials. Microstructural characterization was also carried out using transmission electron microscopy on selected BOR-60 specimens irradiated to ≈25 dpa. No voids were observed in irradiated austenitic stainless steels and cast stainless steels, while a few voids were found in base and grain-boundary-engineered Alloy 690. All the irradiated microstructures were dominated by a high density of Frank loops, which varied in mean size and density for different alloys.
Download or read book Irradiation assisted stress corrosion cracking of austenitic stainless steels written by Takashi Tsukada and published by . This book was released on 1998 with total page 187 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Report on Stress corrosion Cracking of Austenitic Chromium nickel Stainless Steels written by American Society for Testing Materials. Committee A-10 on Iron-Chromium, Iron-Chromium-Nickel, and Related Alloys and published by . This book was released on 1960 with total page 108 pages. Available in PDF, EPUB and Kindle. Book excerpt:
