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Comparison Of Irradiation Induced Shifts Of Kjc And Charpy Impact Toughness For Reactor Pressure Vessel Steels
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Book Synopsis Comparison of Irradiation-Induced Shifts of KJC and Charpy Impact Toughness for Reactor Pressure Vessel Steels by : M. A. Sokolov
Download or read book Comparison of Irradiation-Induced Shifts of KJC and Charpy Impact Toughness for Reactor Pressure Vessel Steels written by M. A. Sokolov and published by . This book was released on 2000-11-01 with total page 115 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Comparison of Irradiation-induced Shifts of Kjc and Charpy Impact Toughness for Reactor Pressure Vessel Steels by : M. A. Sokolov
Download or read book Comparison of Irradiation-induced Shifts of Kjc and Charpy Impact Toughness for Reactor Pressure Vessel Steels written by M. A. Sokolov and published by . This book was released on 2000 with total page 69 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Effects of Radiation on Materials by : R. K. Nanstad
Download or read book Effects of Radiation on Materials written by R. K. Nanstad and published by ASTM International. This book was released on 1999 with total page 1135 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Comparison of Transition Temperature Shifts Between Static Fracture Toughness and Charpy-v Impact Properties Due to Irradiation and Post-Irradiation Annealing for Japanese A533B-1 Steels by : M. Suzuki
Download or read book Comparison of Transition Temperature Shifts Between Static Fracture Toughness and Charpy-v Impact Properties Due to Irradiation and Post-Irradiation Annealing for Japanese A533B-1 Steels written by M. Suzuki and published by . This book was released on 2001 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: It is assumed in the integrity analysis of reactor pressure vessel (RPV) that the irradiation-induced shift of fracture toughness in the ductile-brittle transition region is the same as the Charpy transition temperature shift. To confirm this assumption, both shifts are compared using irradiated and post-irradiation annealed RPV steels made by Japanese manufacturers. Five ASTM A533B class 1 plates having high- and low-level impurities, which correspond to first generation and modern Japanese reactors are used in this study. Neutron irradiation of precracked Charpy-v (PCCv) specimens as well as standard Charpy-v specimens was carried out at the Japan Materials Testing Reactor (JMTR). The values of fast neutron fluence for this study are 2 to 13x1019 (n/cm2, E>1MeV) considering typical fluence values at the EOL and extended operation of Japanese PWRs. The irradiation temperature was controlled within the range of 290±10°C. Thermal annealing treatments at 350°C and 450°C for 100 hours were performed for irradiated PCCv and Charpy-v specimens. The master curve approach according to ASTM Test Method for Determination of Reference Temperature, T0, for Ferritic Steels in the Transition Range (E1921) was applied using PCCv specimens. The irradiation-induced shifts of the reference temperature, ?T0, obtained in this study were spread in the range of 10 to 200°C. The annealing recoveries of the reference temperature were compared with those of the Charpy transition temperature. Although large scatter was seen in the relation between ?T0 values and Charpy 41J shifts, both shifts were almost the same in the average.
Book Synopsis Effects of Radiation on Materials by : Martin L. Grossbeck
Download or read book Effects of Radiation on Materials written by Martin L. Grossbeck and published by ASTM International. This book was released on 2004 with total page 767 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Comprehensive Nuclear Materials by :
Download or read book Comprehensive Nuclear Materials written by and published by Elsevier. This book was released on 2020-07-22 with total page 4871 pages. Available in PDF, EPUB and Kindle. Book excerpt: Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field
Book Synopsis Effects of Radiation on Materials by : Stan T. Rosinski
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 Synopsis Fatigue and Fracture Mechanics by : Ravinder Chona
Download or read book Fatigue and Fracture Mechanics written by Ravinder Chona and published by ASTM International. This book was released on 2002 with total page 408 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Structural Alloys for Nuclear Energy Applications by : Robert Odette
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 673 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.
Book Synopsis Materials Issues for Generation IV Systems by : Véronique Ghetta
Download or read book Materials Issues for Generation IV Systems written by Véronique Ghetta and published by Springer Science & Business Media. This book was released on 2008-04-23 with total page 596 pages. Available in PDF, EPUB and Kindle. Book excerpt: Global warming, shortage of low-cost oil resources and the increasing demand for energy are currently controlling the world's economic expansion while often opposing desires for sustainable and peaceful development. In this context, atomic energy satisfactorily fulfills the criteria of low carbon gas production and high overall yield. However, in the absence of industrial fast-breeders the use of nuclear fuel is not optimal, and the production of high activity waste materials is at a maximum. These are the principal reasons for the development of a new, fourth generation of nuclear reactors, minimizing the undesirable side-effects of current nuclear energy production technology while increasing yields by increasing operation temperatures and opening the way for the industrial production of hydrogen through the decomposition of water. The construction and use of such reactors is hindered by several factors, including performance limitations of known structural materials, particularly if the life of the projected systems had to extend over the periods necessary to achieve low costs (at least 60 years). This book collects lectures and seminars presented at the homonymous NATO ASI held in autumn 2007 at the Institut d’Etudes Scientifiques in Cargèse, France. The adopted approach aims at improving and coordinating basic knowledge in materials science and engineering with specific areas of condensed matter physics, the physics of particle/matter interaction and of radiation damage. It is our belief that this methodology is crucially conditioning the development and the industrial production of new structural materials capable of coping with the requirements of these future reactors.
Book Synopsis Annual session // Indian Institute of Chemical Engineers ; 36 by :
Download or read book Annual session // Indian Institute of Chemical Engineers ; 36 written by and published by . This book was released on 1984 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Understanding and Mitigating Ageing in Nuclear Power Plants by : Philip G Tipping
Download or read book Understanding and Mitigating Ageing in Nuclear Power Plants written by Philip G Tipping and published by Elsevier. This book was released on 2010-10-26 with total page 953 pages. Available in PDF, EPUB and Kindle. Book excerpt: Plant life management (PLiM) is a methodology focussed on the safety-first management of nuclear power plants over their entire lifetime. It incorporates and builds upon the usual periodic safety reviews and licence renewals as part of an overall framework designed to assist plant operators and regulators in assessing the operating conditions of a nuclear power plant, and establishing the technical and economic requirements for safe, long-term operation. Understanding and mitigating ageing in nuclear power plants critically reviews the fundamental ageing-degradation mechanisms of materials used in nuclear power plant structures, systems and components (SSC), along with their relevant analysis and mitigation paths, as well as reactor-type specific PLiM practices. Obsolescence and other less obvious ageing-related aspects in nuclear power plant operation are also examined in depth. Part one introduces the reader to the role of nuclear power in the global energy mix, and the importance and relevance of plant life management for the safety regulation and economics of nuclear power plants. Key ageing degradation mechanisms and their effects in nuclear power plant systems, structures and components are reviewed in part two, along with routes taken to characterise and analyse the ageing of materials and to mitigate or eliminate ageing degradation effects. Part three reviews analysis, monitoring and modelling techniques applicable to the study of nuclear power plant materials, as well as the application of advanced systems, structures and components in nuclear power plants. Finally, Part IV reviews the particular ageing degradation issues, plant designs, and application of plant life management (PLiM) practices in a range of commercial nuclear reactor types. With its distinguished international team of contributors, Understanding and mitigating ageing in nuclear power plants is a standard reference for all nuclear plant designers, operators, and nuclear safety and materials professionals and researchers. Introduces the reader to the role of nuclear power in the global energy mix Reviews the fundamental ageing-degradation mechanisms of materials used in nuclear power plant structures, systems and components (SSC) Examines topics including elimination of ageing effects, plant design, and the application of plant life management (PLiM) practices in a range of commercial nuclear reactor types
Book Synopsis Proceedings of the ASME Pressure Vessels and Piping Conference--2006: Operations, applications, and components by :
Download or read book Proceedings of the ASME Pressure Vessels and Piping Conference--2006: Operations, applications, and components written by and published by . This book was released on 2007 with total page 730 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Comparison of Static and Dynamic Transition Temperature Shifts in VVR Reactor Pressure Vessel Steels by : P. Novosad
Download or read book Comparison of Static and Dynamic Transition Temperature Shifts in VVR Reactor Pressure Vessel Steels written by P. Novosad and published by . This book was released on 2000 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper summarizes results from surveillance specimen programs of VVER-440/V-213C type reactors. Transition temperature shifts, induced by irradiation, and determined from impact Charpy V-notch toughness as well as from static fracture toughness tests on pre-cracked Charpy size specimens, (COD) are compared. Two methods have been used for determination of static fracture toughness shifts -- standard COD type specimens from standard surveillance programs and reconstituted COD type specimens from broken halves of Charpy V-notch specimens; thus identical irradiation conditions have been assured. Results obtained are discussed from the point of view of irradiation conditions as well as of different type of testing. Additional tests have been performed on different heats from WER-1000 type steel, where Charpy V-notch impact and static as well as dynamic fracture toughness tests have been performed to determine transition temperature shifts. Results are discussed and show that transition temperature shifts from static tests are, generally, larger than those from dynamic tests.
Download or read book Technical Reports Series written by and published by . This book was released on 2005 with total page 1086 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis New products for sale from the Superintendent of Documents by :
Download or read book New products for sale from the Superintendent of Documents written by and published by . This book was released on 1999 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Comparison of Irradiation-Induced Transition Temperature Increases from Notch Ductility and Fracture Toughness Tests by : AL. Hiser
Download or read book Comparison of Irradiation-Induced Transition Temperature Increases from Notch Ductility and Fracture Toughness Tests written by AL. Hiser and published by . This book was released on 1987 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt: Reactor pressure vessel (RPV) surveillance capsules contain Charpy-V notch ductility Cv specimens, but many do not contain fracture toughness specimens; accordingly, the radiation-induced shift (increase) in the brittle-to-ductile transition region ?T is based upon the ?T determined from Cv tests. Since the American Society of Mechanical Engineers (ASME) KIc and KIR reference fracture toughness curves are shifted by the ?T from Cv, assurance that this ?T does not underestimate ?T associated with the actual irradiated fracture toughness is required to provide confidence that safety margins do not fall below assumed levels.
