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Book Microstructural Evolution of Reduced Activation and Conventional Martensitic Steels After Thermal Aging and Neutron Irradiation

Download or read book Microstructural Evolution of Reduced Activation and Conventional Martensitic Steels After Thermal Aging and Neutron Irradiation written by M-H Mathon and published by . This book was released on 2001 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Small Angle Neutron Scattering Study of Irradiated Martensitic Steels

Download or read book Small Angle Neutron Scattering Study of Irradiated Martensitic Steels written by M-H Mathon and published by . This book was released on 2005 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: Martensitic/ferritic steels (containing 7-13 % Cr) are candidate materials for internal structures in pressurized water, fast breeder, and fusion reactors. Approval for use requires verification of structural stability under neutron irradiation in relation to the evolution of mechanical properties. In this context, several conventional and Reduced Activation (RA) martensitic materials were neutron irradiated at 325°C up to 6 dpa. They were investigated by Small Angle Neutron Scattering (SANS) under a magnetic field after various doses.

Book Effects of Radiation on Materials

Download or read book Effects of Radiation on Materials written by Stan T. Rosinski and published by ASTM International. This book was released on 2001 with total page 879 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 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 Evolution of Martensitic Steels During Fast Neutron Iradiation

Download or read book Microstructural Evolution of Martensitic Steels During Fast Neutron Iradiation written by and published by . This book was released on 1989 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation of martensitic/ferritic steels with fast neutrons (E> 0.1 MeV) to displacement damage levels of 30--50 dpa at temperatures of 300--500°C produces significant changes in the as-tempered microstructure. Dislocation loops and networks can be produced, irradiation-induced precipitates can form, the lath/subgrain boundary structure and the thermal precipitates produced during tempering can become unstable, and if helium is present, bubbles and voids can form. These microstructural changes caused by irradiation can have important effects on the properties of this class of steels for both fast breeder reactor (FBR) and magnetic fusion reactor (MFR) applications. The purpose of this paper is to compare reactor-irradiated and long-term thermally aged 9Cr--1MoVNb specimens, in order to distinguish effects due to displacement damage from those caused by elevated-temperature exposure alone. 7 refs., 1 fig.

Book Comparison of the Effects of Long term Thermal Aging and HFIR Irradiation on the Microstructural Evolution of 9Cr 1MoVNb Steel

Download or read book Comparison of the Effects of Long term Thermal Aging and HFIR Irradiation on the Microstructural Evolution of 9Cr 1MoVNb Steel written by and published by . This book was released on 1990 with total page 47 pages. Available in PDF, EPUB and Kindle. Book excerpt: Both thermal aging at 482--704°C for up to 25,000h and HFIR irradiation at 300--600°C for up to 39 dpa produce substantial changes in the as-tempered microstructure of 9Cr-1MoVNb martensitic/ferritic steel. However, the changes in the dislocation/subgrain boundary and the precipitate structures caused by thermal aging or neutron irradiation are quite different in nature. During thermal aging, the as-tempered lath/subgrain boundary and carbide precipitate structures remain stable below 650°C, but coarsen and recover somewhat at 650--704°C. The formation of abundant intergranular Laves phase, intra-lath dislocation networks, and fine dispersions of VC needles are thermal aging effects that are superimposed upon the as-tempered microstructure at 482--593°C. HFIR irradiation produces dense dispersions of very small black-dot'' dislocations loops at 300°C and produces helium bubbles and voids at 400°C At 300--500°C, there is considerable recovery of the as-tempered lath/subgrain boundary structure and microstructural/microcompositional instability of the as-tempered carbide precipitates during irradiation. By contrast, the as-tempered microstructure remains essentially unchanged during irradiation at 600°C. Comparison of thermally aged with irradiation material suggests that the instabilities of the as-tempered lath/subgrain boundary and precipitate structures at lower irradiation temperatures are radiation-induced effects, whereas the absence of both Laves phase and fine VC needles during irradiation is a radiation-retarded thermal effect.

Book Radiation induced Changes in Microstructure

Download or read book Radiation induced Changes in Microstructure written by F. A. Garner and published by ASTM International. This book was released on 1987 with total page 919 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 1995 with total page 782 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Chemical Abstracts

Download or read book Chemical Abstracts written by and published by . This book was released on 2002 with total page 2566 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Response of Ferritic Martensitic Steels to Neutrons at Irradiation Temperatures from 20 to 823 K

Download or read book Response of Ferritic Martensitic Steels to Neutrons at Irradiation Temperatures from 20 to 823 K written by Hideki Matsui and published by . This book was released on 1990 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: The objectives of this work are to evaluate mechanical property changes by means of small specimen testing techniques, to evaluate the influence of the cascade damage produced by 14-MeV neutrons from RTNS-II on microstructural evolution, and to understand mechanical property changes in term of microstructural evolution at irradiation temperatures of from 20 to 823 K.

Book High chromium Ferritic and Martensitic Steels for Nuclear Applications

Download or read book High chromium Ferritic and Martensitic Steels for Nuclear Applications written by R. L. Klueh and published by ASTM International. This book was released on 2001-01-01 with total page 221 pages. Available in PDF, EPUB and Kindle. Book excerpt: This monograph reviews the development of high-chromium ferritic/martensitic steels for exposure to the high-energy neutron environment of a fission or fusion reactor, and considers their potential use as a component material. The basic properties of the steels under non-nuclear conditions are provi

Book Correlation Between Creep Properties and Microstructure of Reduced Activation Ferritic Martensitic Steels

Download or read book Correlation Between Creep Properties and Microstructure of Reduced Activation Ferritic Martensitic Steels written by H. Sakasegawa and published by . This book was released on 2001 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: Reduced activation ferritic steels (RAFs), JLF-1 (9Cr-2W-V,Ta steel) had been studied as one of the reference materials in the IEA RAF R&D activity, because of its superior resistance to high-fluence neutron irradiation up to 100 dpa.

Book Effects of Microstructure and Thermal Aging on Neutron Irradiation Embrittlement of 21   4Cr 1Mo Steel for a Nuclear Pressure Vessel

Download or read book Effects of Microstructure and Thermal Aging on Neutron Irradiation Embrittlement of 21 4Cr 1Mo Steel for a Nuclear Pressure Vessel written by M. Suzuki and published by . This book was released on 1987 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Plate, weld, and heat-affected zone (HAZ) materials of 21⁄4Cr-1Mo steels, designated as ASTM A387 Grade 22 Cl.1, and Cl.2 were irradiated at around 400°C to a fluence of about 2 x 1018 n/cm2 (E > 1 MeV). A387 Grade 22 Cl.2 with bainite has a lower susceptibility to neutron irradiation embrittlement than A387 Grade 22 Cl.1 with ferrite plus bainite. The anomalous ductile to brittle transition behavior of A387 Grade 22 Cl.2 was explained by taking into account the parameter ky, which is a constant in the Cottrell-Petch equation. It is concluded that there does not exist any strong interaction between thermal aging embrittlement and neutron irradiation embrittlement.

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 Structural Materials for Generation IV Nuclear Reactors

Download or read book Structural Materials for Generation IV Nuclear Reactors written by Pascal Yvon and published by Woodhead Publishing. This book was released on 2016-08-27 with total page 686 pages. Available in PDF, EPUB and Kindle. Book excerpt: Operating at a high level of fuel efficiency, safety, proliferation-resistance, sustainability and cost, generation IV nuclear reactors promise enhanced features to an energy resource which is already seen as an outstanding source of reliable base load power. The performance and reliability of materials when subjected to the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors are essential areas of study, as key considerations for the successful development of generation IV reactors are suitable structural materials for both in-core and out-of-core applications. Structural Materials for Generation IV Nuclear Reactors explores the current state-of-the art in these areas. Part One reviews the materials, requirements and challenges in generation IV systems. Part Two presents the core materials with chapters on irradiation resistant austenitic steels, ODS/FM steels and refractory metals amongst others. Part Three looks at out-of-core materials. Structural Materials for Generation IV Nuclear Reactors is an essential reference text for professional scientists, engineers and postgraduate researchers involved in the development of generation IV nuclear reactors. - Introduces the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors and implications for structural materials - Contains chapters on the key core and out-of-core materials, from steels to advanced micro-laminates - Written by an expert in that particular area

Book Microstructural Effects of Neutron Irradiation on Ferritic martensitic Stainless Steels

Download or read book Microstructural Effects of Neutron Irradiation on Ferritic martensitic Stainless Steels written by Terence Stuart Morgan and published by . This book was released on 1992 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: