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Book The Influence of Pre irradiation Heat Treatments on Thermal Non equilibrium and Radiation induced Segregation Behavior in Model Austenitic Stainless Steel Alloys

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.

Book The Influence of Pre Irradiation Heat Treatments on Thermal Non Equilibrium and Radiation Induced Segregation Behavior in Model Austenitic Stainless Steel Alloys

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 GS. Was and published by . This book was released on 2004 with total page 13 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 four 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 then 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.

Book Effects of Radiation on Materials

Download or read book Effects of Radiation on Materials written by Martin L. Grossbeck and published by ASTM International. This book was released on 2004 with total page 767 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book ASM Handbook

Download or read book ASM Handbook written by ASM International. Handbook Committee and published by . This book was released on 1990 with total page 1178 pages. Available in PDF, EPUB and Kindle. Book excerpt: These volumes cover the properties, processing, and applications of metals and nonmetallic engineering materials. They are designed to provide the authoritative information and data necessary for the appropriate selection of materials to meet critical design and performance criteria.

Book Corrosion resistant Materials for Extreme Conditions

Download or read book Corrosion resistant Materials for Extreme Conditions written by and published by . This book was released on 2005 with total page 276 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Modelling of Combined Radiation Induced and Thermal Non Equilibrium Segregation of Chromium in Neutron Irradiated Austenitic Stainless Steels

Download or read book The Modelling of Combined Radiation Induced and Thermal Non Equilibrium Segregation of Chromium in Neutron Irradiated Austenitic Stainless Steels written by CC. Goodwin and published by . This book was released on 1999 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: A model of the radiation-induced segregation (RIS) and thermal non- equilibrium segregation (TNES) at grain boundaries has been established within a phenomenological theory. This model indicates that the magnitude and extent of segregation is dependent upon the formation of solute-point defect complexes that migrate to grain boundaries. Theoretical predictions are made for the TNES and RIS of chromium in austenitic stainless steels for the first time. The results indicate that for TNES, chromium creates a positive binding energy in the complex, and is thus enriched at the grain boundary. For RIS, chromium produces a negative binding energy in the complex, and is thus depleted at the grain boundary. The combined effect of the two segregation mechanisms is discussed in relation to the evolution of the segregation profile exhibited by the grain boundary. The segregation profiles are shown to be illustrative of analytically measured profiles for similarly treated materials.

Book Irradiation Effects in Structural Alloys for Thermal and Fast Reactors

Download or read book Irradiation Effects in Structural Alloys for Thermal and Fast Reactors written by and published by ASTM International. This book was released on with total page 437 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Scientific and Technical Aerospace Reports

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1992 with total page 1556 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Metals Abstracts

Download or read book Metals Abstracts written by and published by . This book was released on 1999 with total page 1014 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Irradiation Effects on the Microstructure on Properties of Metals

Download or read book Irradiation Effects on the Microstructure on Properties of Metals written by ASTM International Symposium on Effects of Radiation on Structural Materials and published by ASTM International. This book was released on 1976 with total page 502 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Radiation induced Grain Boundary Segregation in Austenitic Stainless Steels

Download or read book Radiation induced Grain Boundary Segregation in Austenitic Stainless Steels written by and published by . This book was released on 1994 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Radiation-induced segregation (RIS) to grain boundaries in Fe-Ni-Cr-Si stainless alloys has been measured as a function of irradiation temperature and dose. Heavy-ion irradiation was used to produce damage levels from 1 to 20 displacements per atom (dpa) at temperatures from 175 to 550°C. Measured Fe, Ni, and Cr segregation increased sharply with irradiation dose (from G to 5 dpa) and temperature (from 175 to about 350°C). However, grain boundary concentrations did not change significantly as dose or temperatures were further increased. Although interfacial compositions were similar, the width of radiation-induced enrichment or depletion profiles increased consistently with increasing dose or temperature. Impurity segregation (Si and P) was also measured, but only Si enrichment appeared to be radiation-induced. Grain boundary Si peaked at levels approaching 10 at% after irradiation doses to 10 dpa at an intermediate temperature of 325°C. No evidence of grain boundary silicide precipitation was detected after irradiation at any temperature. Equilibrium segregation of P was measured in the high-P alloys, but interfacial concentration did not increase with irradiation exposure. Comparisons to reported RIS in neutron-irradiated stainless steels revealed similar grain boundary compositional changes for both major alloying and impurity elements.

Book Effects of Radiation on Substructure and Mechanical Properties of Metals and Alloys

Download or read book Effects of Radiation on Substructure and Mechanical Properties of Metals and Alloys written by John Moteff and published by ASTM International. This book was released on 1973 with total page 560 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Effects of Radiation on Substructure and Mechanical Properties of Metals and Alloys

Download or read book Effects of Radiation on Substructure and Mechanical Properties of Metals and Alloys written by and published by ASTM International. This book was released on 1973 with total page 546 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Effect of Radiation Induced Segregation on Precipitate Stability and Swelling in Irradiated Alloys

Download or read book Effect of Radiation Induced Segregation on Precipitate Stability and Swelling in Irradiated Alloys written by VA. Pechenkin and published by . This book was released on 1999 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: The radiation-induced segregation of alloy components near point defect sinks with a particular attention to Fe-Cr-Ni based alloys is analyzed. The influence of point defect generation rate on temperature ranges of stability for radiation-retarded M23C6 and radiation-induced Ni3Si precipitates in austenitic stainless steels is considered. A method of calculation of steady-state segregation-induced bias in irradiated binary alloys, taking into account Kirkendall forces and drift forces caused by point defect migration and formation energy gradients near sinks, is proposed. Contributions of various forces to the bias in Fe-Cr-Ni and V-Fe alloys are evaluated. The effect of void-precipitate association on swelling is analyzed. The radiation-induced segregation of components and segregation-induced bias for motionless and moving grain boundaries in a Fe-Cr-Ni alloy are calculated by solving the set of coupled diffusion equations for component and point defect concentrations.

Book Development of a Robust Modeling Tool for Radiation induced Segregation in Austenitic Stainless Steels

Download or read book Development of a Robust Modeling Tool for Radiation induced Segregation in Austenitic Stainless Steels written by and published by . This book was released on 2015 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation-assisted stress corrosion cracking (IASCC) of austenitic stainless steels in Light Water Reactor (LWR) components has been linked to changes in grain boundary composition due to irradiation induced segregation (RIS). This work developed a robust RIS modeling tool to account for thermodynamics and kinetics of the atom and defect transportation under combined thermal and radiation conditions. The diffusion flux equations were based on the Perks model formulated through the linear theory of the thermodynamics of irreversible processes. Both cross and non-cross phenomenological diffusion coefficients in the flux equations were considered and correlated to tracer diffusion coefficients through Manning's relation. The preferential atomvacancy coupling was described by the mobility model, whereas the preferential atom-interstitial coupling was described by the interstitial binding model. The composition dependence of the thermodynamic factor was modeled using the CALPHAD approach. Detailed analysis on the diffusion fluxes near and at grain boundaries of irradiated austenitic stainless steels suggested the dominant diffusion mechanism for chromium and iron is via vacancy, while that for nickel can swing from the vacancy to the interstitial dominant mechanism. The diffusion flux in the vicinity of a grain boundary was found to be greatly influenced by the composition gradient formed from the transient state, leading to the oscillatory behavior of alloy compositions in this region. This work confirms that both vacancy and interstitial diffusion, and segregation itself, have important roles in determining the microchemistry of Fe, Cr, and Ni at irradiated grain boundaries in austenitic stainless steels.

Book Modeling the Effects of Oversize Solute Additions on Radiation Induced Segregation in Austenitic Stainless Steels

Download or read book Modeling the Effects of Oversize Solute Additions on Radiation Induced Segregation in Austenitic Stainless Steels written by GS. Was and published by . This book was released on 2005 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Oversize solute additions to stainless steels hold promise for reducing radiation-induced segregation (RIS), possibly delaying the onset and severity of irradiation-assisted stress-corrosion cracking (IASCC). The Modified Inverse Kirkendall (MIK) model for RIS in austenitic stainless steels was adapted to include the effects of defect trapping, which is expected to be caused by oversized solutes, on RIS. The model accounts for the sensitivity of RIS to both dose rate and temperature. Model results show that the primary contribution to the reduction in RIS occurs through vacancy trapping and recombination with migrating interstitials, requiring strong solute binding energies on the order of 1.0 eV. The maximum reduction in RIS due to defect trapping increases with dose rate and temperature. The general trends of the model are consistent with experimental data from proton and neutron irradiations.