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Author : W. L. Server
Publisher :
ISBN 13 :
Total Pages : 138 pages
Book Rating : 4.E/5 ( download)
Download or read book An Approach for Predicting Reference Fracture Toughness in Irradiated Vessel Materials written by W. L. Server and published by . This book was released on 1988 with total page 138 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : William L. Server
Publisher :
ISBN 13 :
Total Pages : 12 pages
Book Rating : 4.:/5 (125 download)
Download or read book Fracture Toughness Shifts and Bounds for Irradiated Reactor Pressure Vessel Materials written by William L. Server and published by . This book was released on 1990 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Transition temperature shift effects arising from neutron radiation embrittlement in ferritic nuclear pressure vessel materials are currently being evaluated using changes in the Charpy V-notch energy curve; typically, the temperature shift at the 41-J (30 ft-lb) energy level is used. Estimates of the 41 J (30 ft-lb) transition temperature are also projected based upon Nuclear Regulatory Commission Regulatory Guide 1.99, Revision 2. The estimated or measured Charpy shift is then applied to a lower-bound reference toughness KIR curve by moving the curve by the Charpy shift amount. Similarly, the flaw evaluation procedures in nonmandatory Appendix A of Section XI of the ASME Boiler and Pressure Vessel Code utilize the shifts in the equivalent of the KIR curve (termed the KIa curve for crack arrest) and a lower-bound static crack initiation toughness KIc curve. This study reviewed and tested this Code's approach, as well as the statistically based reference toughness method developed by W. Oldfield for estimating global tolerance bounds. Comparisons of actual, but limited, fracture toughness data and the predicted bounding curves indicate that the shifted KIR/KIc curves are generally very conservative. The Oldfield reference toughness approach for 95%-95% tolerance bounds is not as conservative, but may provide a better method. In terms of mean toughness shift behavior, the shifts predicted by Charpy V-notch results are not always a true indicator of the mean fracture toughness shift; however, the other margins included in Regulatory Guide 1.99, Revision 2 and those in the original unirradiated KIR/KIc curves appear to compensate for any nonconservatism in using the Charpy V-notch shift approach.
Author : Roger E. Stoller
Publisher : ASTM International
ISBN 13 : 080311477X
Total Pages : 1315 pages
Book Rating : 4.8/5 (31 download)
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
Author :
Publisher :
ISBN 13 :
Total Pages : 578 pages
Book Rating : 4.0/5 ( download)
Download or read book Energy Research Abstracts written by and published by . This book was released on 1993-10 with total page 578 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : RG. Lott
Publisher :
ISBN 13 :
Total Pages : 11 pages
Book Rating : 4.:/5 (125 download)
Download or read book The Technical Foundations of a Unified Adjusted Reference Temperature for RPV Fracture Toughness written by RG. Lott and published by . This book was released on 2004 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: The use of a reference temperature to define the transition from ductile-to-brittle behavior is a well-established practice in reactor pressure vessel integrity analysis. Current procedures for analysis of irradiated pressure vessel steels use an Adjusted Reference Temperature (ART or RTPTS) that shift the unirradiated RTDNT value based on Charpy data and apply additional margins. The recent adoption of an ASTM Standard Test Method for Determination of Reference Temperature, To, for Ferritic Steels in the Transition Range (E 1921) has made direct determinations of fracture toughness reference temperature in irradiated materials using Master Curve feasible. ASME Code Case N629 recognizes the potential of this new technology as an alternative means of determining an ART value for use in reactor pressure vessel integrity analysis. This alternative approach has been used in recent plant specific submittals to the NRC. ASTM sub-committee E10.02 is currently considering adopting a standard to provide a unified definition of the Adjusted Reference Temperature. This unified definition would provide consistent procedures for using either RTNDT or Master Curve based definitions of ART. This unified definition would provide common margins for the two approaches and assure a consistent level of confidence in the analysis. The statistical basis of the Master Curve makes it possible to establish a more rational basis for the margins applied in both approaches.
Author : Lendell E. Steele
Publisher : ASTM International
ISBN 13 : 0803114788
Total Pages : 405 pages
Book Rating : 4.8/5 (31 download)
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:
Author : American Society of Mechanical Engineers. Winter Annual Meeting
Publisher :
ISBN 13 :
Total Pages : 114 pages
Book Rating : 4.3/5 (91 download)
Download or read book Reference Fracture Toughness Procedures Applied to Pressure Vessel Materials written by American Society of Mechanical Engineers. Winter Annual Meeting and published by . This book was released on 1984 with total page 114 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : KK. Yoon
Publisher :
ISBN 13 :
Total Pages : 11 pages
Book Rating : 4.:/5 (125 download)
Download or read book Comparison of Fracture Toughness of Irradiated Reactor Vessel Welds -- Predicted by ASTM E 900 and Measured written by KK. Yoon and published by . This book was released on 2000 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: Recently, a new predictive model has been developed by the NRC and is being implemented in ASTM Standard E 900, that addresses radiation-induced embrittlement of ferritic steels. The model is based on extensive Charpy impact energy data of irradiated reactor vessel steels obtained from surveillance programs. The final application of this new method is to predict fracture toughness of irradiated materials to determine pressure-temperature curves for nuclear power plant operation and RTPTS values in compliance with the current regulatory rules for the nuclear-utility industry.
Author : Ravinder Chona
Publisher : ASTM International
ISBN 13 : 080311429X
Total Pages : 187 pages
Book Rating : 4.8/5 (31 download)
Download or read book Rapid Load Fracture Testing written by Ravinder Chona and published by ASTM International. This book was released on 1992 with total page 187 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : TR. Mager
Publisher :
ISBN 13 :
Total Pages : 8 pages
Book Rating : 4.:/5 (125 download)
Download or read book Irradiated Dynamic and Arrest Fracture Toughness Compared to Lower-Bound Predictions written by TR. Mager and published by . This book was released on 1992 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: Pressure-temperature operating curves for nuclear reactor pressure vessels are based upon a lower-bound fracture toughness curve which bounds rapid load dynamic initiation and crack arrest fracture toughness data. The ASME Boiler and Pressure Vessel Code defines the reference toughness (KIR) curve as this lower bound, and this KIR curve was developed solely from unirradiated dynamic and arrest fracture toughness data from one heat of SA533B-1 steel (HSST Plate 02) and two heats of SA508-2 steel. The effects of radiation embrittlement on the shape and shift of the KIR curve to account for the increase in reference temperature is thought to be conservative, but this conservatism has not been fully verified. This study reviews available data from past dynamic and arrest toughness tests on irradiated vessel steels from test reactor irradiations and compares the data to the shifted KIR curve using the transition temperature shift approach detailed in Regulatory Guide 1.99, Revision 2. Dynamic initiation and crack arrest fracture toughness data are available from only a few irradiated large specimen tests (that is, test specimens with thicknesses greater than about 51 mm [2 in.]); small specimen tests (including precracked Charpy) are used for the other comparisons. The limited results indicate that the Regulatory approach for shifting the KIR curve is very conservative even when the Regulatory Guide 1.99, Revision 2 "margin term" is not used and a correction for fluence rate is ignored. No change in shape for the dynamic toughness and arrest data (in particular for low upper shelf materials) was observed.
Author : American Society of Mechanical Engineers. Winter Annual Meeting
Publisher :
ISBN 13 :
Total Pages : 122 pages
Book Rating : 4.:/5 (89 download)
Download or read book Reference Fracture Toughness Procedures Applied to Pressure Vessel Materials written by American Society of Mechanical Engineers. Winter Annual Meeting and published by . This book was released on 1984 with total page 122 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : P. R. Abelkis
Publisher : ASTM International
ISBN 13 : 9780803107144
Total Pages : 500 pages
Book Rating : 4.1/5 (71 download)
Download or read book Design of Fatigue and Fracture Resistant Structures written by P. R. Abelkis and published by ASTM International. This book was released on 1982 with total page 500 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : RK. Nanstad
Publisher :
ISBN 13 :
Total Pages : 13 pages
Book Rating : 4.:/5 (125 download)
Download or read book Application of Reference Toughness Curves to the HSSI Fifth Irradiation Series written by RK. Nanstad and published by . This book was released on 1992 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: The reference toughness technique, developed under the sponsorship of the Electric Power Research Institute (EPRI), is utilized to predict radiation-induced changes in fracture toughness of reactor vessel steels using Charpy impact data from the Heavy Section Steel Irradiation (HSSI) program. The results of the prediction are compared (1) with the data from the HSSI Fifth Irradiation Series large-compact fracture toughness specimens, (2) to the predictions of shifting the KIc curve using Regulatory Guide 1.99, Revision 2 (RG 1.99, Rev. 2), and (3) to the predictions of shifting the KIc curve using the change in the 41-J transition temperature of the HSSI Fifth Irradiation Series Charpy data. The EPRI reference toughness approach provides a reasonable prediction of fracture toughness on the lower shelf and in the low transition, but is a poor predictor of the upper transition fracture toughness. Improvements to the EPRI reference toughness methodology are suggested. It is also observed that although the 41-J (30 ft-lb) shift methodology underpredicts the mean shift in the HSSI Fifth Irradiation Series fracture toughness data, the RG 1.99, Rev. 2 shift, when two sets of Charpy data are not available, provides a conservative bound to the measured HSSI fracture toughness data with considerable margin.
Author :
Publisher :
ISBN 13 :
Total Pages : 600 pages
Book Rating : 4.0/5 ( download)
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1974 with total page 600 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Naoki Soneda
Publisher : Elsevier
ISBN 13 : 0857096478
Total Pages : 437 pages
Book Rating : 4.8/5 (57 download)
Download or read book Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants written by Naoki Soneda and published by Elsevier. This book was released on 2014-09-01 with total page 437 pages. Available in PDF, EPUB and Kindle. Book excerpt: Reactor Pressure Vessels (RPVs) contain the fuel and therefore the reaction at the heart of nuclear power plants. They are a life-determining structural component: if they suffer serious damage, the continued operation of the plant is in jeopardy. This book critically reviews irradiation embrittlement, the main degradation mechanism affecting RPV steels, and mitigation routes for managing the RPV lifetime. Part I reviews RPV design and fabrication in different countries, with an emphasis on the materials required, their important properties, and manufacturing technologies. Part II then considers RVP embrittlement in operational nuclear power plants using different reactors. Chapters are devoted to embrittlement in light-water reactors, including WWER-type reactors and Magnox reactors. Finally, Part III presents techniques for studying embrittlement, including irradiation simulation techniques, microstructural characterisation techniques, and probabilistic fracture mechanics. Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants provides a thorough review of an issue that is central to the safety of nuclear power generation. The book includes contributions from an international team of experts, and will be a useful resource for nuclear plant operators and managers, relevant regulatory and safety bodies, nuclear metallurgists and other academics in this field Discusses reactor pressure vessel (RPV) design and the effect irradiation embrittlement can have, the main degradation mechanism affecting RPVs Examines embrittlement processes in RPVs in different reactor types, as well as techniques for studying RPV embrittlement
Author :
Publisher : Elsevier
ISBN 13 : 0081028660
Total Pages : 4871 pages
Book Rating : 4.0/5 (81 download)
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
Author :
Publisher :
ISBN 13 :
Total Pages : 212 pages
Book Rating : 4.3/5 (91 download)
Download or read book LWR Pressure Vessel Surveillance Dosimetry Improvement Program written by and published by . This book was released on 1979-10 with total page 212 pages. Available in PDF, EPUB and Kindle. Book excerpt:
