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Semiempirical Model For Annealing And Reirradiation Embrittlement In Pressure Vessel Steels
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Book Synopsis Semiempirical Model for Annealing and Reirradiation Embrittlement in Pressure Vessel Steels by : RG. Lott
Download or read book Semiempirical Model for Annealing and Reirradiation Embrittlement in Pressure Vessel Steels written by RG. Lott and published by . This book was released on 1989 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: A model of recovery and reembrittlement in an annealed nuclear reactor pressure vessel steel is described. Modeling is an integral part of the overall approach to annealing because it provides a bridge between the experimental studies and the application of the results to actual pressure vessels. This model is based on a series of annealing and reirradiation studies performed using microhardness specimens. Most of these materials were originally irradiated in nuclear pressure vessel surveillance programs. The model is based on the concept of a benefit factor, which compares the annealed and unirradiated specimens to material that has been irradiated without an intermediate anneal. It is noted that the data can most reasonably be explained by assuming that the mechanism of annealing is a combination of reversible and nonreversible processes. This model can be used to predict transition temperature shifts in annealed materials.
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 276 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Evaluation of System Requirements and Standards Development for Thermal Annealing of Reactor Pressure Vessels by : W. L. Server
Download or read book Evaluation of System Requirements and Standards Development for Thermal Annealing of Reactor Pressure Vessels written by W. L. Server and published by . This book was released on 1983 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Effects of Radiation on Materials by : D. S. Gelles
Download or read book Effects of Radiation on Materials written by D. S. Gelles and published by ASTM International. This book was released on 1996 with total page 1169 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Effects of Radiation on Materials by : Roger E. Stoller
Download or read book Effects of Radiation on Materials written by Roger E. Stoller and published by ASTM International. This book was released on 1992 with total page 1315 pages. Available in PDF, EPUB and Kindle. Book excerpt: Symposium held in Nashville, Tennessee, June 1990. Almost two-thirds of these 91 papers are authored by researchers outside of the US (including information on research in the former USSR, Japan, and Europe). Topics include: current commercial power reactor systems; microstructural characterization
Book Synopsis Assuring Structural Integrity of Steel Reactor Pressure Boundary Components by : K. E. Stahlkopf
Download or read book Assuring Structural Integrity of Steel Reactor Pressure Boundary Components written by K. E. Stahlkopf and published by . This book was released on 1988 with total page 396 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Effects of Radiation on Materials by :
Download or read book Effects of Radiation on Materials written by and published by . This book was released on 1996 with total page 1192 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Annual Book of ASTM Standards by : ASTM International
Download or read book Annual Book of ASTM Standards written by ASTM International and published by . This book was released on 2004 with total page 1268 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A Study of the Mechanical Property Changes of Irradiation Embrittled Pressure Vessel Steels and Their Response to Annealing Treatments by :
Download or read book A Study of the Mechanical Property Changes of Irradiation Embrittled Pressure Vessel Steels and Their Response to Annealing Treatments written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Dependence of Re-embrittlement Rate After Annealing on the Copper, Nickel and Phosphorus Contents in Model Alloys by : M. Valo
Download or read book Dependence of Re-embrittlement Rate After Annealing on the Copper, Nickel and Phosphorus Contents in Model Alloys written by M. Valo and published by . This book was released on 2004 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation embrittlement rate as well as the re-embrittlement rate after annealing of pressure vessel steels can in general be described by the copper, phosphorus and nickel contents of the materials. In the current study embrittlement and re-embrittlement rate of 32 different model alloys were measured using sub-size CH-V specimens of dimensions 3 × 4 × 27 mm. The impurity and alloy elements of the model alloys were varied within the limits Cu: 0−1.0 wt-%, P = 0−0.040 wt-% and Ni: 0−2.0 wt-% relatively evenly. The specimens were originally irradiated in the high flux reactor in Petten into a neutron fluence of 0.3×1019n/cm2, E >1 MeV and re-irradiated after the annealing treatment in the Loviisa power reactor into a fluence of 1.0 × 1019n/cm2, E > 1 MeV. In the paper the irradiation and re-irradiation embrittlement rate has been modeled based on the Cu, P and Ni contents of the alloys. Re-irradiation rate was found to be clearly lower than the original irradiation rate except for small corner in the element space, i.e., no nickel, low copper and high phosphorus alloys. Phosphorus coefficient in the re-irradiation shift function is relatively two times higher than in the original irradiation shift function. Many of the alloys in the IAI-condition show intergranular type fracture (IGF). However, the effect of the change of the fracture mode from cleavage to IGF on transition temperature shift remains open. The dependence of irradiation embrittlement, annealing and re-embrittlement behavior on the copper, phosphorus and nickel contents is still not solved, one reason being the relatively limited variation of the key elements in the materials. Model alloys offer a good variation matrix of the elements even, if the measured data cannot be directly applied to real steels.
Download or read book INIS Atomindex written by and published by . This book was released on 1987 with total page 1068 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis LWRSP FY09 Testing and Analysis of Reactor Metal Degradation by :
Download or read book LWRSP FY09 Testing and Analysis of Reactor Metal Degradation written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Current regulations require RPV steels to maintain conservative margins of fracture toughness so that postulated flaws do not threaten the integrity of the RPV during either normal operation and maintenance cycles or under accident transients, like pressurized thermal shock. Neutron irradiation degrades fracture toughness, in some cases severely. Thermal aging, while not generally considered a significant issue for a 40-y operating life, must be an additional consideration for operation to 60 or 80 years. Regulations, codified in the ASME Boiler and Pressure Vessel Code, Regulatory Guide 1.99 Rev 2, etc., recognize that embrittlement has a potential for reducing toughness below acceptable levels. The last few decades have seen remarkable progress in developing a mechanistic understanding of irradiation embrittlement. This understanding has been exploited in formulating robust, physically-based and statistically-calibrated models of CVN-indexed transition-temperature shifts (TTS). These semi-empirical models account for key embrittlement variables and variable interactions, including the effects of copper (Cu), nickel (Ni), phosphorous (P), fluence ([phi]t), flux ([phi]), and irradiation temperature (T{sub i}). However, these models and our present understanding of radiation damage are not fully quantitative, and do not treat all potentially significant variables and issues. Over the past three decades, developments in fracture mechanics have led to a number of consensus standards and codes for determining the fracture toughness parameters needed for development of databases that are useful for statistical analysis and establishment of uncertainties. The CVN toughness, however, is a qualitative measure, which must be correlated with the fracture toughness and crack-arrest toughness properties, K{sub Ic} and K{sub Ia}, necessary for structural integrity evaluations. Where practicable, direct measurements of the fracture toughness properties are desirable to reduce the uncertainties associated with correlations. Moreover, fracture-toughness data have been obtained in sufficient quantity to permit probabilistic application. The progress notwithstanding, however, there are still significant technical issues that need to be addressed to reduce the uncertainties in regulatory application. The major issues regarding irradiation effects are summarized in [1,2]. Of the many significant issues discussed, those deemed to have the most impact on the current regulatory process are: (1) high fluence, long irradiation times, and flux effects, (2) material variability and surrogate materials, (3) high-nickel materials, (4) the fracture toughness master curve, (5) the bias in reference toughness derived from precracked Charpy specimens, (6) attenuation, (7) modeling and microstructural analysis, (8) thermal annealing and reirradiation, and (9) thermal aging. Material variability and surrogate materials are an overarching issue. A more complete understanding of the other issues is needed in order to reduce the uncertainties associated with material variability. Moreover, the combination of irradiation experiments with modeling and microstructural studies provides an essential element in aging evaluations of RPVs. It is clear that embrittlement of RPV steels is a critical issue that may limit LWR plant life extension. The primary objective of the LWRSP RPV task is to develop robust predictions of transition temperature shifts (TTS) at high fluence ([phi]t) to at least 1020 n/cm2 (>1 MeV) pertinent to plant operation for 80 full power years. New and existing databases will be combined to support developing physically based models of TTS for high fluence-low flux ([phi]
Download or read book Physics Briefs written by and published by . This book was released on 1980 with total page 982 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fundamentals of Radiation Materials Science by : GARY S. WAS
Download or read book Fundamentals of Radiation Materials Science written by GARY S. WAS and published by Springer. This book was released on 2016-07-08 with total page 1014 pages. Available in PDF, EPUB and Kindle. Book excerpt: The revised second edition of this established text offers readers a significantly expanded introduction to the effects of radiation on metals and alloys. It describes the various processes that occur when energetic particles strike a solid, inducing changes to the physical and mechanical properties of the material. Specifically it covers particle interaction with the metals and alloys used in nuclear reactor cores and hence subject to intense radiation fields. It describes the basics of particle-atom interaction for a range of particle types, the amount and spatial extent of the resulting radiation damage, the physical effects of irradiation and the changes in mechanical behavior of irradiated metals and alloys. Updated throughout, some major enhancements for the new edition include improved treatment of low- and intermediate-energy elastic collisions and stopping power, expanded sections on molecular dynamics and kinetic Monte Carlo methodologies describing collision cascade evolution, new treatment of the multi-frequency model of diffusion, numerous examples of RIS in austenitic and ferritic-martensitic alloys, expanded treatment of in-cascade defect clustering, cluster evolution, and cluster mobility, new discussion of void behavior near grain boundaries, a new section on ion beam assisted deposition, and reorganization of hardening, creep and fracture of irradiated materials (Chaps 12-14) to provide a smoother and more integrated transition between the topics. The book also contains two new chapters. Chapter 15 focuses on the fundamentals of corrosion and stress corrosion cracking, covering forms of corrosion, corrosion thermodynamics, corrosion kinetics, polarization theory, passivity, crevice corrosion, and stress corrosion cracking. Chapter 16 extends this treatment and considers the effects of irradiation on corrosion and environmentally assisted corrosion, including the effects of irradiation on water chemistry and the mechanisms of irradiation-induced stress corrosion cracking. The book maintains the previous style, concepts are developed systematically and quantitatively, supported by worked examples, references for further reading and end-of-chapter problem sets. Aimed primarily at students of materials sciences and nuclear engineering, the book will also provide a valuable resource for academic and industrial research professionals. Reviews of the first edition: "...nomenclature, problems and separate bibliography at the end of each chapter allow to the reader to reach a straightforward understanding of the subject, part by part. ... this book is very pleasant to read, well documented and can be seen as a very good introduction to the effects of irradiation on matter, or as a good references compilation for experimented readers." - Pauly Nicolas, Physicalia Magazine, Vol. 30 (1), 2008 “The text provides enough fundamental material to explain the science and theory behind radiation effects in solids, but is also written at a high enough level to be useful for professional scientists. Its organization suits a graduate level materials or nuclear science course... the text was written by a noted expert and active researcher in the field of radiation effects in metals, the selection and organization of the material is excellent... may well become a necessary reference for graduate students and researchers in radiation materials science.” - L.M. Dougherty, 07/11/2008, JOM, the Member Journal of The Minerals, Metals and Materials Society.
Book Synopsis Integrity of Reactor Pressure Vessels in Nuclear Power Plants by :
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.
Book Synopsis Nuclear Power Plant Life Management and Longer-term Operation by : OECD Nuclear Energy Agency
Download or read book Nuclear Power Plant Life Management and Longer-term Operation written by OECD Nuclear Energy Agency and published by OECD Publishing. This book was released on 2006 with total page 68 pages. Available in PDF, EPUB and Kindle. Book excerpt: On cover and title page: Nuclear development
Book Synopsis Small Specimen Test Techniques by : W. R. Corwin
Download or read book Small Specimen Test Techniques written by W. R. Corwin and published by ASTM International. This book was released on 1998 with total page 630 pages. Available in PDF, EPUB and Kindle. Book excerpt: As part of an increasing interest in radiation embrittlement for aging nuclear reactors, scientists gathered in New Orleans in January 1997 to consider the interests and capabilities of the scientific-testing community and of the commercial light-water-cooled power-reactor industry in terms of improving methods to characterize component integrity. The resulting 37 papers concentrate on the use of unique small and miniature specimens; nondestructive, nonintrusive, and in- situ test techniques for measuring mechanical and fracture properties; the application of tests to irradiation-induced embrittlement; and actual examples of tests to determine material integrity and to evaluate potential component life extension. They consider experimental, analytical, and computational aspects. Annotation copyrighted by Book News, Inc., Portland, OR
