Download or read book Irradiation Assisted Stress Corrosion Cracking and Grain Boundary Segregation in Heat Treated Type 304 SS written by RE. Clausing and published by . This book was released on 1990 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Evidence was obtained correlating the susceptibility of Type 304 (UNS 530400) stainless steel (SS) to irradiation-assisted stress corrosion cracking (IASCC) and grain boundary segregation. Susceptibility to IASCC was measured in constant extension rate tensile (CERT) tests, and grain boundary segregation was demonstrated by Auger electron spectroscopy and HNO3/Cr+6 corrosion tests.
Download or read book Effects of Radiation on Materials written by N. H. Packan and published by ASTM International. This book was released on 1990 with total page 679 pages. Available in PDF, EPUB and Kindle. Book excerpt: Annotation Effects of Radiation on Materials: Fourteenth International Symposium was presented at Andover, MA, June 1988. The symposium was sponsored by ASTM Committee E-10 on Nuclear Technology and Applications. The papers from the first three days of the symposium appear in the two volumes of this publication. Volume I encompasses radiation damage- induced microstructures; point defect, solute, and gas atom effects; atomic-level measurement techniques; and applications of theory. Volume II includes mechanical behavior, all papers dealing with pressure-vessel steels, breeder reactor components, dosimetry, and nuclear fuels. The fourth day of the symposium was devoted to the single topic of reduced-activation materials (see TK9204). The two volumes are separately sold at $127 and $128 respectively; each is independently indexed. Annotation copyrighted by Book News, Inc., Portland, OR.
Download or read book Effects of Impurities on Stress Corrosion Cracking in Type 316NG Stainless Steel written by William Dale Miller and published by . This book was released on 1985 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Environmentally Assisted Cracking written by R. D. Kane and published by ASTM International. This book was released on 2000 with total page 491 pages. Available in PDF, EPUB and Kindle. Book excerpt: The November 2000 symposium addressed methodologies for evaluation of environmental assisted cracking (EAC) in equipment and structures exposed to corrosive environments, and recent developments in the generation of relevant materials properties data based on laboratory tests. Twenty-seven papers fr
Download or read book Irradiation induced Sensitization and Stress Corrosion Cracking of Type 304 Stainless Steel Core internal Components written by and published by . This book was released on 1991 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: High- and commercial-purity heats of Type 304 stainless steel, obtained from neutron absorber tubes after irradiation to fluence levels of up to 2 x 1021 n{center dot}cm−2 (E> 1 MeV) in two boiling water reactors, were examined by Auger electron spectroscopy to characterize irradiation-induced grain- boundary segregation and depletion of alloying and impurity elements. Segregation of Si, P, Ni, and an unidentified element or compound that gives rise to an Auger energy peak at 59 eV was observed in the commercial-purity heat. Such segregation was negligible in high-purity material, except for Ni. No evidence of S segregation was observed in either material. Cr depletion was more pronounced in the high-purity material than in the commercial-purity material. These observations suggest a synergism between the significant level of impurities and Cr depletion in the commercial-purity heat. In the absence of such synergism, Cr depletion appears more pronounced in the high-purity heat. Initial results of constant-extension-rate tests conducted on the two heats in air an in simulated BWR water were correlated with the results from analysis by Auger electron spectroscopy. 15 refs., 10 figs.
Download or read book Effects of Radiation on Materials written by Arvind S. Kumar and published by ASTM International. This book was released on 1994 with total page 1319 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 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 Isolation of the Role of Radiation induced Segregation in Irradiation assisted Stress Corrosion Cracking of Proton irradiated Austenitic Stainless Steels written by Jeremy Todd Busby and published by . This book was released on 2001 with total page 1008 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Stress Corrosion Cracking the Slow Strain rate Technique written by G. M. Ugiansky and published by ASTM International. This book was released on 1979 with total page 446 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Stress Corrosion Cracking Susceptibility of Irradiated Type 304 Stainless Steels written by and published by . This book was released on 1992 with total page 19 pages. 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.
Download or read book Corrosion of Stainless Steels written by A. John Sedriks and published by John Wiley & Sons. This book was released on 1996-04-19 with total page 467 pages. Available in PDF, EPUB and Kindle. Book excerpt: A Complete, Up-to-Date Introduction to Corrosion of StainlessSteels and Metallurgical Factors This fully updated Second Editionof Corrosion of Stainless Steels covers the tremendous advancesmade with stainless steels in recent decades, includingapplications in many new areas--from marine technologies andoff-shore oil production to power plants and the kitchen sink. Thisbook offers unique insights into the corrosion mechanisms affectingstainless steels, details problem-avoidance strategies, and helpsidentify corrosion-resistant capabilities for these remarkablealloys Sponsored by the Electrochemical Society, Corrosion osStainless Steels * Provides a comprehensive introduction to the selection,development, and production of all types of stainless steels * Emphasizes how metallurgical factors affect corrosionresistance * Examines the limitations of stainless steels within the contextof a discussion on higher alloys * Takes an interdisciplinary approach that demonstrates thecombined effects of metallurgy, chemistry, and electrochemistry oncorrosion resistance * Provides baseline knowledge and testing standards for stainlesssteels, and facilitates failure analysis for industrial purposes orlitigation related to equipment failure This is a much-needed text for materials scientists, chemicalengineers, corrosion specialists, graduate students, and anyone whoneeds to be brought up to date on this subject.
Download or read book Stress Corrosion Cracking Susceptibility of Irradiated Type 304 Stainless Steels written by HM. Chung and published by . This book was released on 1994 with total page 19 pages. 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.
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1995 with total page 704 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Radiation Induced Solute Segregation and Stress Corrosion Cracking Study of AISI 304 and AISI 304L Stainless Steels written by WJ. Liu and published by . This book was released on 1994 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt: Radiation induced solute segregation (RIS) of chromium, nickel, and minor elements (e.g., Si, P, S, etc.) in the vicinity of grain boundaries and its influences on intergranular stress corrosion cracking (IGSCC) of commercial purity AISI 304 and AISI 304L austenitic stainless steels were investigated in this study. High energy protons were used for producing irradiation environment.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1994 with total page 444 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Irradiation induced Sensitization of Austenitic Stainless Steel In core Components written by and published by . This book was released on 1990 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: High- and commercial-purity specimens of Type 304 SS from BWR absorber rod tubes, irradiated during service to fluence levels of 6 x 102° to 2 x 1021 n{center dot}cm−2 (E> 1 MeV) in two reactors, were examined by Auger electron spectroscopy to characterize irradiation-induced grain boundary segregation and depletion of alloying and impurity elements, which have been associated with irradiation-assisted stress corrosion cracking (IASCC) of the steel. Ductile and intergranular fracture surfaces were produced by bending of hydrogen-charged specimens in the ultra-high vacuum of Auger microscope. The intergranular fracture surfaces in high-fluence commercial-purity material were characterized by relatively high levels of Si, P, and In segregation. An Auger energy peak at 59 eV indicated either segregation of an unidentified element or formation of an unidentified compound on the grain boundary. In contrast to the commercial-purity material, segregation of the impurity elements and intergranular failure in the high-purity material were negligible for a similar fluence level. However, grain boundary depletion of Cr was more significant in high-purity material than in commercial-purity material, which indicates that irradiation-induced segregation of impurity elements and depletion of alloying elements are interdependent. 7 refs., 10 figs., 2 tabs.
Download or read book The Influence of Pre irradiation Heat Treatments on Thermal Non equilibrium and Radiation induced Segregation Behavior in Model Austenitic Stainless Steel Alloys written by and published by . This book was released on 2002 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effect of pre-irradiation heat treatments on thermal non-equilibrium grain boundary segregation (TNES) and subsequent radiation-induced grain boundary segregation (RIS) is studied in a series of model austenitic stainless steels. The alloys used for this study are based on AISI 316 stainless steel and have the following nominal compositions: Fe-16Cr-13Ni-1.25Mn (base 316), Fe-16Cr-13Ni-1.25Mn-2.0Mo (316 + Mo) and Fe-16Cr-13Ni-1.25Mn-2.0Mo-0.07P (316 + Mo + P). Samples were heat treated at temperatures ranging from 1100 to 1300 C and cooled at 4 different rates (salt brine quench, water quench, air cool and furnace cool) to evaluate the effect of annealing temperature and quench rate on TNES. The alloys were than processed with the treatment (temperature and cooling rate) that resulted in the maximum Cr enrichment. Alloys with and without the heat treatment to enrich the grain boundaries with Cr were characterized following irradiation to 1 dpa at 400 C with high-energy protons in order to understand the influence of alloying additions and pre-irradiation grain boundary chemistry on irradiation-induced elemental enrichment and depletion profiles. Various mechanistic models will be examined to explain the observed behavior.
