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Book Characterization of Phosphorus Segregation in Neutron irradiated Pressure Vessel Steels by Atom Probe Field Ion Microscopy

Download or read book Characterization of Phosphorus Segregation in Neutron irradiated Pressure Vessel Steels by Atom Probe Field Ion Microscopy written by and published by . This book was released on 1995 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt: An atom probe field ion microscopy characterization of A533B and Russian VVER 440 and 1000 pressure vessel steels has been performed to determine the phosphorus coverage of grain and lath boundaries. Field ion micrographs of grain and lath boundaries have revealed that they are decorated with a semi-continuous film of discrete brightly-imaging precipitates that were identified as molybdenum carbonitride precipitates. In addition, extremely high phosphorus levels were measured at the boundaries. The phosphorus segregation was found to be confined to an extremely narrow region indicative of monolayer-type segregation. The phosphorus coverages determined from the atom probe results of the unirradiated materials were in excellent agreement with predictions based on McLean's equilibrium model of grain boundary segregation. The boundary phosphorus coverage of a neutron-irradiated weld material was significantly higher than that observed in the unirradiated material.

Book An APFIM Survey of Grain Boundary Segregation and Precipitation in Irradiated Pressure Vessel Steels

Download or read book An APFIM Survey of Grain Boundary Segregation and Precipitation in Irradiated Pressure Vessel Steels written by MG. Burke and published by . This book was released on 1994 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: Atom probe field ion microscopy has revealed that excessive copper levels in pressure vessel steels result in the formation of ultrafine copper-enriched clusters and precipitates during in-service neutron irradiation. In addition to these important clusters and precipitates, this technique has revealed many other fine-scaled microstructural features in these steels. These microstructural features may be divided into two broad categories; 1) intragranular precipitates and clusters and 2) interfacial segregation. The precipitates and clusters include spherical, rod-shaped and disk-shaped molybdenum and vanadium carbides, disk-shaped molybdenum nitrides, and spherical iron oxides. The type of precipitate is dependent on the metallic additions that are made to the various types of steels used in the pressure vessel. Some of these features are present in approximately the same number density and size as the copper clusters and precipitates and will therefore make a contribution to the mechanical properties. The characterization of grain boundaries and precipitate/matrix interfaces has revealed a complex pattern of segregation of various solutes including phosphorus, nickel and manganese.

Book Fine Scale Microstructural Characterization of Pressure Vessel Steels and Related Materials Using APFIM

Download or read book Fine Scale Microstructural Characterization of Pressure Vessel Steels and Related Materials Using APFIM written by Michael K. Miller and published by . This book was released on 1990 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt: Atom probe field-ion microscopy has been used to characterize the ultrafine microstructure of neutron-irradiated A302B and A212B pressure vessel steels, A533B submerged arc welds, and several model Fe-Cu alloys. The atomic spatial resolution of this technique permits a complete microstructural and chemical description of the ultrafine features that control the mechanical properties to be made. A variety of ultrafine features, including roughly spherical and disc-shaped copper precipitates and clusters, copper atmospheres, copper phosphides, phosphorus clusters, spherical and rod-shaped molybdenum carbides, molybdenum phosphides, disc-shaped molybdenum nitrides, and iron nitride precipitates, were observed in these materials. The presence of these features was found to be material dependent. The atom probe also revealed a complex pattern of segregation and precipitation at grain boundaries and segregation to precipitate-ferrite interfaces.

Book Microstructure of Irradiated Materials  Volume 373

Download or read book Microstructure of Irradiated Materials Volume 373 written by Ian M. Robertson and published by . This book was released on 1995-04-03 with total page 600 pages. Available in PDF, EPUB and Kindle. Book excerpt: The focus of the symposium, which was held at the 1994 MRS Fall Meeting, was on the changes produced in the microstructure of metals, ceramics, and semiconductors by irradiation with energetic particles. This proceedings volume contains invited and contributed papers. Among the topics are computer simulation of displacement cascade damage in metals; radiation effects in ceramic insulators; and computer simulation of thermal annealing effects of self implanted silicon. Annotation copyright by Book News, Inc., Portland, OR

Book Microstructural Characterization of Irradiated PWR Steels Using the Atom Probe Field ion Microscope

Download or read book Microstructural Characterization of Irradiated PWR Steels Using the Atom Probe Field ion Microscope written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Atom probe field-ion microscopy has been used to characterize the microstructure of a neutron-irradiated A533B pressure vessel steel weld. The atomic spatial resolution of this technique permits a complete structural and chemical description of the ultra-fine features that control the mechanical properties to be made. A variety of fine scale features including roughly spherical copper precipitates and clusters, spherical and rod-shaped molybdenum carbide and disc-shaped molybdenum nitride precipitates were observed to be inhomogeneously distributed in the ferrite. The copper content of the ferrite was substantially reduced from the nominal level. A thin film of molybdenum carbides and nitrides was observed on grain boundaries in addition to a coarse copper-manganese precipitate. Substantial enrichment of manganese and nickel were detected at the copper-manganese precipitate-ferrite interface and this enrichment extended into the ferrite. Enrichment of nickel, manganese and phosphorus were also measured at grain boundaries.

Book Effects of Radiation on Materials

Download or read book Effects of Radiation on Materials written by Todd R. Allen and published by ASTM International. This book was released on 2006 with total page 411 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Microstructural Characterization of Irradiated Fe Cu Ni P Model Steels

Download or read book Microstructural Characterization of Irradiated Fe Cu Ni P Model Steels written by and published by . This book was released on 1987 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: The microstructure of Fe-Cu-Ni-P model pressure vessel steels after neutron irradiation and thermal aging has been characterized by atom probe field-ion microscopy and augmented by transmission electron microscopy. High densities of small, roughly spherical or disc shaped copper clusters/precipitates were observed in the neutron irradiated alloys that contained copper. Small spherical phosphorus clusters were observed in the irradiated copper-free alloys, and copper phosphides were observed in a high phosphorus Fe-Cu-Ni-P alloy. None of these clusters/precipitates were observed in the thermally aged materials. The increases in the tensile and yield strengths that were observed after neutron irradiation resulted from these clusters and other lattice defects.

Book Metals Abstracts

Download or read book Metals Abstracts written by and published by . This book was released on 1996 with total page 764 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Phosphorus Segregation and Intergranular Embrittlement in Thermally Aged and Neutron Irradiated Reactor Pressure Vessel Steels

Download or read book Phosphorus Segregation and Intergranular Embrittlement in Thermally Aged and Neutron Irradiated Reactor Pressure Vessel Steels written by Masahide Suzuki and published by . This book was released on 2007 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: A study on phosphorus (P) segregation at grain boundaries and intergranular embrittlement of reactor pressure vessel steels due to thermal aging and neutron irradiation has been performed for A533B steel plates and weld metals doped with different bulk levels of P. The initial P concentration at grain boundaries of these materials determined by scanning Auger microscopy ranged from 9 to 33 %. The materials thermally aged at temperatures ranging from 450 to 550°C for up to 10000 h exhibited increases in P concentration described by the McLean's equation. A linear correlation was obtained between P concentration and Charpy 41 J transition temperature (T41J). Fracture toughness tests in the ductile-to-brittle transition temperature region have been conducted by the Master Curve method using 1T-CT specimens. The material subject to intergranular embrittlement exhibited the dual fracture toughness distributions typically observed in inhomogeneous materials. This was probably due to two types of initiation of cleavage and intergranular fracture. The lower tail analysis based on the Master Curve method enabled conservative fracture toughness estimates by fitting the lower fracture toughness arising from intergranular fracture. The relation between median KJc values estimated from the lower tail analysis and temperature appeared to follow the Master Curve. For neutron irradiated materials up to a fluence of 6.9×1019 n/cm2 (E>1 MeV) at 290°C by the Japan Materials Testing Reactor, an increase in grain boundary P segregation associated with decrease in carbon segregation was observed with increasing fluence. Relative significant hardening was recognized for the material with high bulk P content. Shifts in the reference temperature T0 and T41J were comparable for the thermally aged and irradiated materials.

Book Effects of Radiation on Materials

Download or read book Effects of Radiation on Materials written by Margaret L. Hamilton and published by ASTM International. This book was released on 2000 with total page 1266 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Review

    Book Details:
  • Author : Oak Ridge National Laboratory
  • Publisher :
  • Release : 1994
  • ISBN :
  • Pages : 580 pages

Download or read book Review written by Oak Ridge National Laboratory and published by . This book was released on 1994 with total page 580 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels

Download or read book Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels written by Lendell E. Steele and published by ASTM International. This book was released on 1993 with total page 405 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Energy Research Abstracts

Download or read book Energy Research Abstracts written by and published by . This book was released on 1992 with total page 886 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Acta Polytechnica Scandinavica

Download or read book Acta Polytechnica Scandinavica written by and published by . This book was released on 1998 with total page 124 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Effects of Radiation on Materials

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:

Book Structural Alloys for Nuclear Energy Applications

Download or read book Structural Alloys for Nuclear Energy Applications written by Robert Odette and published by Newnes. This book was released on 2019-08-15 with total page 676 pages. Available in PDF, EPUB and Kindle. Book excerpt: High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors' unique personal insight from decades of frontline research, engineering and management. - Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. - Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. - Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.