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Deformation Behavior In Reactor Pressure Vessel Steels As A Clue To Understanding Irradiation Hardening
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Book Synopsis Deformation Behavior in Reactor Pressure Vessel Steels as a Clue to Understanding Irradiation Hardening by :
Download or read book Deformation Behavior in Reactor Pressure Vessel Steels as a Clue to Understanding Irradiation Hardening written by and published by . This book was released on 1999 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: In this paper, we examine the post-yield true stress vs true strain behavior of irradiated pressure vessel steels and iron-based alloys to reveal differences in strain-hardening behavior associated with different irradiating particles (neutrons and electrons) and different alloy chernky. It is important to understand the effects on mechanical properties caused by displacement producing radiation of nuclear reactor pressure steels. Critical embrittling effects, e.g. increases in the ductile-to-brittle-transition-temperature, are associated with irradiation-induced increases in yield strength. In addition, fatigue-life and loading-rate effects on fracture can be related to the post-irradiation strain-hardening behavior of the steels. All of these properties affect the expected service life of nuclear reactor pressure vessels. We address the characteristics of two general strengthening effects that we believe are relevant to the differing defect cluster characters produced by neutrons and electrons in four different alloys: two pressure vessel steels, A212B and A350, and two binary alloys, Fe-0.28 wt%Cu and Fe-0.74 wt%Ni. Our results show that there are differences in the post-irradiation mechanical behavior for the two kinds of irradiation and that the differences are related both to differences in damage produced and alloy chemistry. We find that while electron and neutron irradiations (at T (less-than or equal to) 60 C) of pressure vessel steels and binary iron-based model alloys produce similar increases in yield strength for the same dose level, they do not result in the same post-yield hardening behavior. For neutron irradiation, the true stress flow curves of the irradiated material can be made to superimpose on that of the unirradiated material, when the former are shifted appropriately along the strain axis. This behavior suggests that neutron irradiation hardening has the same effect as strain hardening for all of the materials analyzed. For electron irradiated steels, the post-yield hardening rate is clearly greater than that of the unirradiated material, and the flow curves cannot be made to superimpose. The binary iron-base model alloys studied here show a less pronounced difference in flow behavior for neutrons and electrons than exhibited by the steels, implicating the effect of alloy chemistry. Our results are analyzed in the context of classical theories dealing with the interaction between the deformation microstructure, i.e. glide dislocations, and irradiation-produced defects. Our findings provide clues about the way different alloy constituents interact with the different kinds of irradiation damage to strengthen the material differently.
Book Synopsis Irradiation Behavior of Reactor Pressure Vessel Steels from the Research Program on the Integrity of Components by : J. Ahlf
Download or read book Irradiation Behavior of Reactor Pressure Vessel Steels from the Research Program on the Integrity of Components written by J. Ahlf and published by . This book was released on 1986 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: Within the research program "Integrity of Components," reactor pressure vessel steels are irradiated in capsules in the swimming-pool-type research reactor FRG-2 at 290°C to different fluences of fast neutrons. Steel heats both conforming and not conforming to specifications with respect to chemical composition as well as to tensile and deformation properties are included.
Book Synopsis Effects of Neutron Irradiation and Temperature on High Strain Rate Behaviour of Reactor Pressure Vessel Steel by : Z. Bílek
Download or read book Effects of Neutron Irradiation and Temperature on High Strain Rate Behaviour of Reactor Pressure Vessel Steel written by Z. Bílek and published by . This book was released on 1982 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper describes the results of an investigation of the influence of neutron irradiation on mechanical properties of a reactor pressure vessel steel at high strain rates ?? ? (103 to 104)s-1 produced by means of the Hopkinson split pressure bar technique (HSPBT). Our steel with chemical composition 0.18% C, 1.22% Mn, 0.012% P, 0.016% S, 0.17% Cr, 0.33% Ni, 0.055% Al, 0.028% Ti was irradiated by fast neutrons to an exposure of 1.35 . 1023 (n)m-2. The extensive dynamic measurements performed in the temperature range of (90 + 573) °K are analysed in terms of state equation for viscoplastic flow. It is shown that neutron irradiation shifts the transition between thermally activated and viscous dislocation damping mechanism of plastic deformation to the higher strain rates. Particular attention is paid to the comparison of the influence of neutron irradiation and strain aging.
Book Synopsis Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels by : Lendell E. Steele
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 1986 with total page 303 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Analysis of the Behaviour of Advanced Reactor Pressure Vessel Steels Under Neutron Irradiation by : International Atomic Energy Agency
Download or read book Analysis of the Behaviour of Advanced Reactor Pressure Vessel Steels Under Neutron Irradiation written by International Atomic Energy Agency and published by . This book was released on 1986 with total page 119 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Mapping Flow Localization Processes in Deformation of Irradiated Reactor Structural Alloys by :
Download or read book Mapping Flow Localization Processes in Deformation of Irradiated Reactor Structural Alloys written by and published by . This book was released on 2002 with total page 63 pages. Available in PDF, EPUB and Kindle. Book excerpt: Metals that can sustain plastic deformation homogeneously throughout their bulk tend to be tough and malleable. Often, however, if a metal has been hardened it will no longer deform uniformly. Instead, the deformation occurs in narrow bands on a microscopic scale wherein stresses and strains become concentrated in localized zones. This strain localization degrades the mechanical properties of the metal by causing premature plastic instability failure or by inducing the formation of cracks. Irradiation with neutrons hardens a metal and makes it more prone to deformation by strain localization. Although this has been known since the earliest days of radiation damage studies, a full measure of the connection between neutron irradiation hardening and strain localization is wanting, particularly in commercial alloys used in the construction of nuclear reactors. Therefore, the goal of this project is to systematically map the extent of involvement of strain localization processes in plastic deformation of three reactor alloys that have been neutron irradiated. The deformation processes are to be identified and related to changes in the tensile properties of the alloys as functions of neutron fluence (dose) and degree of plastic strain. The intent is to define the role of strain localization in radiation embrittlement phenomena. The three test materials are a tempered bainitic A533B steel, representing reactor pressure vessel steel, an annealed 316 stainless steel and annealed Zircaloy-4 representing reactor internal components.
Book Synopsis Radiation Hardening and Embrittlement in a Reactor Pressure Vessel Steel by : R. G. Berggreen
Download or read book Radiation Hardening and Embrittlement in a Reactor Pressure Vessel Steel written by R. G. Berggreen and published by . This book was released on 1969 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt: The relationship between the increase in tensile yield stress (YS) and the increase in the ductile-brittle transition temperature (DBTT) upon irradiation was studied for ASTM A 212-65 Grade B pressure vessel steel. Smooth tension specimens and Charpy V-notch impact specimens were irradiated in the same facility of the Oak Ridge Research Reactor under the same conditions of 60 C irradiation temperature and 1 x 1010 neutrons/cm2 (E > 1 MeV) fluence. The tension tests were carried out at temperatures from 20 to 473 K at two strain rates. The YS increased rapidly with decreasing test temperature, but the radiation-produced increment in YS was largely independent of test temperature. The impact specimens also were tested as a function of temperature and the increase in DBTT was determined based on absorbed energy and fracture appearance. To correlate the changes in YS and DBTT upon irradiation, strain-rate and triaxiality corrections were applied to the tensile yield stresses to approximate the corresponding stresses at the root of the notch of the impact specimens. The results of the tension and impact tests were found to be consistent, based on a critical cleavage stress deduced from the tension tests. No evidence for a decrease in the critical cleavage stress upon irradiation was noted.
Book Synopsis The Role of Some Alloying Elements on Radiation Hardening in Pressure Vessel Steels by : N. Igata
Download or read book The Role of Some Alloying Elements on Radiation Hardening in Pressure Vessel Steels written by N. Igata and published by . This book was released on 1973 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Recent trends in nuclear-pressure-vessel steels for light-water reactors have been toward Ni-Cr-Mo steels. The effect of minor elements--for example, copper and phosphorus--also has been investigated. In this study, the role of nickel, chromium, molybdenum, and copper was investigated to understand the irradiation behavior of pressure vessel steel, using internal friction measurement, transmission electron microscopy (TEM), and mechanical testing. The materials used were Fe-1Ni, Fe-0.25Cr, Fe-0.5Mo, and Fe-0.2Cu. They were annealed or quenched and irradiated 1 ~ 3 x 1019 nvt(>1MeV) at 60 C (140 F), and postirradiation annealing was performed in the range 150~450 C (302~842 F).
Book Synopsis Irradiation Behaviour of Reactor Pressure Vessel Steels from the Research Program on the Integrity of Components by : Jürgen Ahlf
Download or read book Irradiation Behaviour of Reactor Pressure Vessel Steels from the Research Program on the Integrity of Components written by Jürgen Ahlf and published by . This book was released on 1987 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Irradiation and Annealing Behavior of 15Kh2MFA Reactor Pressure Vessel Steel by : U. Bergmann
Download or read book Irradiation and Annealing Behavior of 15Kh2MFA Reactor Pressure Vessel Steel written by U. Bergmann and published by . This book was released on 1993 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt: This work deals with the mechanical properties of reactor pressure vessel (RPV) steels used in the pressurized water reactors (PWR) of former Soviet type WWER-440. The materials under investigation were a forging (base metal 15Kh2MFA) and the corresponding weld. Charpy V-notch specimens and tensile test specimens were irradiated in the PWR WWER-2 Rheinsberg at about 270°C up to the two neutron fluence levels of 4 x 1018 and 5 x 1019 n/cm2 (E > 1 MeV). Post irradiation annealing heat treatments were performed, among others a 475°C/152 h treatment of technical interest.
Book Synopsis Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels by : Lendell E. Steele
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 1989 with total page 296 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Irradiation Embrittlement of Reactor Pressure Vessel Steels Due to Mechanisms Other Than Radiation Hardening by : BA. Gurovich
Download or read book Irradiation Embrittlement of Reactor Pressure Vessel Steels Due to Mechanisms Other Than Radiation Hardening written by BA. Gurovich and published by . This book was released on 1999 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt: Data on Russian pressure vessel steels in unirradiated, irradiated and annealed conditions are presented. The experimental methods applied included impact testing, fractography, electron microscopy and Auger spectroscopy. Contributions from different mechanisms to radiation embrittlement were evaluated. These studies enabled us to conclude that the major contribution to radiation induced ductile-to-brittle transitions temperature shift in Russian pressure vessel steels is delivered by mechanisms other than radiation hardening.
Book Synopsis Analysis of the Behaviour of Advanced Reactor Pressure Vessel Steels Under Neutron Irradiation by :
Download or read book Analysis of the Behaviour of Advanced Reactor Pressure Vessel Steels Under Neutron Irradiation written by and published by . This book was released on 1983 with total page 315 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Microstructural and Mechanical Characterization of Radiation Effects in Model Reactor Pressure Vessel Steels by : H-W Viehrig
Download or read book Microstructural and Mechanical Characterization of Radiation Effects in Model Reactor Pressure Vessel Steels written by H-W Viehrig and published by . This book was released on 2005 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper presents results of radiation-induced nanoscale microstructural changes measured by Small-Angle Neutron Scattering (SANS) on ASTM-type reactor pressure vessel (RPV) steels. Five different base metals and one weld metal were investigated. The irradiation was performed in a VVER-type power reactor to three different dose levels, maximally 0.14 dpa, at an irradiation temperature of 255°C. The volume content of the micostructural features measured is correlated with the irradiation hardening and embrittlement.
Book Synopsis Evaluation of Thermal Annealing Behavior of Neutron-Irradiated Reactor Pressure Vessel Steels Using Nondestructive Test Methods by : G. Brauer
Download or read book Evaluation of Thermal Annealing Behavior of Neutron-Irradiated Reactor Pressure Vessel Steels Using Nondestructive Test Methods written by G. Brauer and published by . This book was released on 1989 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: Usually the assessment of the irradiation sensitivity and annealing behavior of reactor pressure vessel (RPV) steels is performed by means of destructive test methods, mainly impact and tension tests. In this paper a new kind of search for an efficient temperature-time regime for postirradiation thermal heat treatment is presented using nondestructive test methods like positron annihilation (Doppler broadening pararneter S) and hardness (Vickers hardness HV 10).
Book Synopsis Modeling the Post-yield Flow Behavior After Neutron and Electron Irradiation of Steels and Iron-base Alloys by :
Download or read book Modeling the Post-yield Flow Behavior After Neutron and Electron Irradiation of Steels and Iron-base Alloys written by and published by . This book was released on 1999 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation hardening is an issue of practical importance as it relates to the remanent life and the nature of failure of reactor components exposed to displacement-producing radiation. For example, irradiation-induced yield strength increases in pressure vessel steels are directly related to increases in the ductile-to-brittle-transition-temperature of these materials. Other issues associated with hardening, such as reductions in ductility, toughness and fatigue life of structural steels are also of concern. Understanding these phenomena requires studies of fundamental microstructural mechanisms of hardening. Because of the limited supply of neutron-irradiated surveillance material, difficulties posed by the radioactivity of neutron-exposed samples and the uncertainty of irradiation conditions in this case, fundamental studies are often conducted using well-controlled experiments involving irradiation by electrons instead of neutrons. Also, in such studies, simple model alloys are used in place of steels to focus on the influence of specific alloy constituents. It is, therefore, important to understand the relationship between the results of this kind of experiment and the effects of in-reactor neutron exposure in order to use them to make predictions of significance to reactor component life. In this paper, we analyze the tensile behavior of pressure vessel steels (A212B and A350) irradiated by neutrons and electrons. The results show that the post-yield true stress/true strain behavior can provide fingerprints of the different hardening effects that result from irradiation by the two particles, which also reflect the influence of alloy content. Microstructurally-based models for irradiation-induced yield strength increases, combined with a model for strain hardening, are used to make predictions of the different effects of irradiation by the two particles on the entire flow curve that agree well with data.
Book Synopsis Analysis of the Behaviour of Advanced Reactor Pressure Vessel Steels Under Neutron Irradiation by : Ajia Keizai Kenkyūjo (Japan)
Download or read book Analysis of the Behaviour of Advanced Reactor Pressure Vessel Steels Under Neutron Irradiation written by Ajia Keizai Kenkyūjo (Japan) and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
