Download or read book Irradiation of Some Pressure Vessel Steels written by L. P. Trudeau and published by . This book was released on 1959 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Irradiation of Some Pressure Vessel Steels written by Atomic Energy of Canada Limited and published by . This book was released on 1959 with total page 35 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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 276 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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:

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:

Download or read book Irradiation Embrittlement of Reactor Pressure Vessel Steels written by Myrddin Davies and published by . This book was released on 2000 with total page 4 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Integrity of Reactor Pressure Vessels in Nuclear Power Plants written by and published by . This book was released on 2009 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication is intended to assist nuclear utilities in optimizing the service life of nuclear power plants. It reviews the latest research on the effects of neutron irradiation on the steels and welds of reactor pressure vessels within light water cooled and moderated reactors.

Download or read book Irradiation Effects at 160 2409C in Some Swedish Pressure Vessel Steels written by M. Grounes and published by . This book was released on 1967 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Nickel on Irradiation Embrittlement of Light Water Reactor Pressure Vessel Steels written by International Atomic Energy Agency and published by IAEA. This book was released on 2005 with total page 70 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication sets out the findings of a co-ordinated research project to determine the influence of the mechanism of the deterioration effect in radiation embrittlement of reactor pressure vessel steels with a high nickel content in nuclear power plants, including procurement of materials, determination of mechanical properties, irradiation and testing of specimens, and microstructural characterisation.

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).

Download or read book Irradiation Effects at 160 240oC in Some Swedish Pressure Vessel Steels written by Mikael Grounes and published by . This book was released on 1967 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Irradiation Tests of Several Steels for Reactor Pressure Vessels written by M. Hasegawa and published by . This book was released on 1969 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt: The first trial irradiation tests of pressure vessel steels scheduled by the Steel Irradiation Joint Committee of Japan (SIJC) were begun in 1963 and completed in 1967.

Download or read book Irradiation Embrittlement of LWR Pressure Vessel Steels written by G. R. Odette and published by . This book was released on 1989 with total page 340 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Radiation Damage of Nuclear Power Plant Pressure Vessel Steels written by Nikolaĭ Nikolaevich Alekseenko and published by . This book was released on 1997 with total page 304 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book describes the current state of knowledge about pressure vessel material selection, fabrication (including welding), the changes in properties in service, and response to high-temperature annealing. In contrast to the bad reports of inadequate attention to reactor safety in the former Soviet Union, this book shows that the question of pressure vessel performance has received proper attention and a strong scientific base underlies the assessment of vessel life. This book should be read by reactor designers and operators and their scientific colleagues throughout the world.

Download or read book Irradiation Effects at 160 2400 C in Some Swedish Pressure Vessel Steels written by Mikael Grounes and published by . This book was released on 1967 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Effect of Flux on the Irradiation Hardening of Pressure Vessel Steels written by CA. English and published by . This book was released on 1994 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt: Hardening of low copper steels irradiated at 288°C increased with increasing flux in the range from about 0.6 to 50 x 1016 n/m2-s. In contrast, the hardening of high copper steels was generally less effected and, in some cases, decreased with increasing flux. Thus there are at least two competing effects of flux. The behavior of low copper alloys is attributed to a population of thermally unstable matrix defects that anneal during irradiation, hence, produce hardening that increases with flux. However, the unstable matrix defects also act as point defect sinks reducing radiation enhanced solute diffusion rates. In high copper steels, lower diffusion rates delay hardening due to precipitation. These conclusions were confirmed by low-temperature post-irradiation annealing treatments which produced rapid recovery of the unstable matrix defects. The observed data trends are consistent with a model that treats the unstable matrix defects as small cascade vacancy clusters.

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.