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Author : H. M. Chung
Release : 1992
Genre :
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Book Synopsis Stress Corrosion Cracking Susceptibility of Irradiated Type 304 Stainless Steels by : H. M. Chung
Download or read book Stress Corrosion Cracking Susceptibility of Irradiated Type 304 Stainless Steels written by H. M. Chung. This book was released on 1992. Available in PDF, EPUB and Kindle. Book excerpt:
Author : HM. Chung
Release : 1994
Genre : Auger electron spectroscopy
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Book Synopsis Stress Corrosion Cracking Susceptibility of Irradiated Type 304 Stainless Steels by : HM. Chung
Download or read book Stress Corrosion Cracking Susceptibility of Irradiated Type 304 Stainless Steels written by HM. Chung. This book was released on 1994. Available in PDF, EPUB and Kindle. Book excerpt: Slow-strain-rate tensile tests and microstructural analysis by Auger electron spectroscopy were conducted on specimens of high- and commercial-purity (HP and CP) heats of Type 304 stainless steel obtained from neutron absorber tubes and a control blade sheath after irradiation up to 2.5x1021 n•cm-2 (E>1 MeV) in boiling water reactors (BWRs). The susceptibility of the HP absorber tubes to intergranular stress corrosion cracking (IGSCC) was higher than that of the CP absorber tubes or the CP control blade sheath. IGSCC susceptibilities of the BWR components could not be correlated with segregation of impurities on grain boundaries. However, for comparable fluence levels, the susceptibilities could be correlated to concentrations of Cr on grain-boundaries.
Author :
Release : 1992
Genre :
Kind : eBook
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Book Synopsis Stress Corrosion Cracking Susceptibility of Irradiated Type 304 Stainless Steels by :
Download or read book Stress Corrosion Cracking Susceptibility of Irradiated Type 304 Stainless Steels written by . This book was released on 1992. Available in PDF, EPUB and Kindle. Book excerpt: Slow-strain-rate tensile tests and microstructural analysis by Auger electron spectroscopy were conducted on specimens of high- and commercial-purity (HP and CP) heats of Type 304 stainless steel obtained from neutron absorber tubes and a control blade sheath after irradiation up to 2.5 [times] 10[sup 2l] n[center dot]cm[sup [minus]2] (E> l MeV) in boiling water reactors (BWRs). The susceptibility of the HP absorber tubes to intergranular stress corrosion cracking (IGSCC) was higher than that of the CP absorber tubes or the CP control blade sheath. IGSCC susceptibilities of the BWR components could not be correlated to segregation impurities on grain boundaries. However for comparable fluence levels, Cr on grain-boundaries.
Author :
Release : 2001
Genre :
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Book Synopsis Tensile Stress Corrosion Cracking of Type 304 Stainless Steel Irradiated to Very High Dose by :
Download or read book Tensile Stress Corrosion Cracking of Type 304 Stainless Steel Irradiated to Very High Dose written by . This book was released on 2001. Available in PDF, EPUB and Kindle. Book excerpt: Certain safety-related core internal structural components of light water reactors, usually fabricated from Type 304 or 316 austenitic stainless steels (SSs), accumulate very high levels of irradiation damage (20--100 displacement per atom or dpa) by the end of life. The data bases and mechanistic understanding of, the degradation of such highly irradiated components, however, are not well established. A key question is the nature of irradiation-assisted intergranular cracking at very high dose, i.e., is it purely mechanical failure or is it stress-commotion cracking? In this work, hot-cell tests and microstructural characterization were performed on Type 304 SS from the hexagonal fuel can of the decommissioned EBR-11 reactor after irradiation to (approximately)50 dpa at (approximately)370 C. Slow-strain-rate tensile tests were conducted at 289 C in air and in water at several levels of electrochemical potential (ECP), and microstructural characteristics were analyzed by scanning and transmission electron microcopies. The material deformed significantly by twinning and exhibited surprisingly high ductility in air, but was susceptible to severe intergranular stress corrosion cracking (IGSCC) at high ECP. Low levels of dissolved O and ECP were effective in suppressing the susceptibility of the heavily irradiated material to IGSCC, indicating that the stress corrosion process associated with irradiation-induced grain-boundary Cr depletion, rather than purely mechanical separation of grain boundaries, plays the dominant role. However, although IGSCC was suppressed, the material was susceptible to dislocation channeling at low ECP, and this susceptibility led to poor work-hardening capability and low ductility.
Author : GS. Was
Release : 2004
Genre : Building materials
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Book Synopsis The Role of Fine Defect Clusters in Irradiation-Assisted Stress Corrosion Cracking of Proton-Irradiated 304 Stainless Steel by : GS. Was
Download or read book The Role of Fine Defect Clusters in Irradiation-Assisted Stress Corrosion Cracking of Proton-Irradiated 304 Stainless Steel written by GS. Was. This book was released on 2004. Available in PDF, EPUB and Kindle. Book excerpt: The influence of small defect clusters on irradiation-assisted stress corrosion cracking (IASCC) of austenitic stainless steels has been examined. A CP-304 SS alloy was irradiated with 3.2 MeV protons to 1.0 dpa at 360°C and then annealed for 45 min. to 1 h at temperatures ranging from 400-600°C. Dislocation microstructure was analyzed using both bright field and dark field techniques and cracking susceptibility was measured in an oxygenated water environment. Intergranular cracking was mitigated following annealing at 500°C/45 min. while only the smallest dislocation loops had been removed. Analysis of the slip step bands on the surface of deformed samples indicates that deformation mode may be important in determining cracking susceptibility. Low-temperature irradiation (
