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Download or read book Improved Embrittlement Correlations For Reactor Pressure Vessel Steels... NUREG/CR-6551... U.S. Nuclear Regulatory Commission written by and published by . This book was released on 1999* with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : E. D. Eason
Publisher :
ISBN 13 : 9780160629709
Total Pages : 127 pages
Book Rating : 4.6/5 (297 download)
Download or read book Improved Embrittlement Correlations for Reactor Pressure Vessel Steels written by E. D. Eason and published by . This book was released on 1998-11-01 with total page 127 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Lendell E. Steele
Publisher : ASTM International
ISBN 13 : 0803111878
Total Pages : 276 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 1989 with total page 276 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 : Lendell E. Steele
Publisher : ASTM International
ISBN 13 : 0803104731
Total Pages : 303 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 1986 with total page 303 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : GE. Lucas
Publisher :
ISBN 13 :
Total Pages : 36 pages
Book Rating : 4.:/5 (125 download)
Download or read book Irradiation Embrittlement of Reactor Pressure Vessel Steels written by GE. Lucas and published by . This book was released on 1986 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt: A model of irradiation embrittlement is described for predicting the 41-J Charpy V-notch temperature shifts (?T) as a function of metallurgical variables and neutron exposure conditions. This forecasting procedure combines semi-empirical physical models with statistical analyses of test and power reactor data, and calibration against data from fundamental experiments in which both mechanical property and microstructural changes are evaluated. The models are based on the evolution of a damage microstructure, which includes both copper precipitates and a radiation damage component enhanced by nickel. The precipitate volume is also increased by nickel and impurity phosphorus. Predicted hardening and shifts associated with these extended defects are based on empirically validated models. The model is able to self-consistently rationalize a wide array of microstructural and mechanical property data for commercial pressure vessel steels as well as model alloys.
Author : Lendell E. Steele
Publisher :
ISBN 13 :
Total Pages : 252 pages
Book Rating : 4.F/5 ( download)
Download or read book Neutron Irradiation Embrittlement of Reactor Pressure Vessel Steels written by Lendell E. Steele and published by . This book was released on 1975 with total page 252 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : ST. Byrne
Publisher :
ISBN 13 :
Total Pages : 17 pages
Book Rating : 4.:/5 (125 download)
Download or read book Refinements to Pressure Vessel Steel Embrittlement Correlations written by ST. Byrne and published by . This book was released on 1999 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: ASTM E 900-87, Standard Guide for Predicting Neutron Radiation Damage to Reactor Vessel Materials, provides methods for predicting the effects of fast neutron irradiation on the toughness of reactor pressure vessel materials. The prediction methodology is similar but separate for the steel base metal and weld metal. The methodology relies on a correlation between the chemical content of the steel and the fast neutron fluence. The prediction methodology is used to assess the margin of safety against fracture of the reactor vessel during normal operation and postulated transients.
Author : WL. Server
Publisher :
ISBN 13 :
Total Pages : 19 pages
Book Rating : 4.:/5 (125 download)
Download or read book A Mechanistically-Guided Charpy Embrittlement Correlation for Reactor Pressure Vessel Integrity Assessment written by WL. Server and published by . This book was released on 2004 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt: The current neutron irradiation embrittlement trend equation used in the U.S. is contained in Nuclear Regulatory Commission (NRC) Regulatory Guide 1.99, Revision 2. The database used to establish this correlation was compiled in the late 1980s. Since that time there has been about a five fold increase in data. Through the EPRI Materials Reliability Program a new and improved transition temperature shift embrittlement correlation has been developed. The recommended model is mechanistically-guided, statistically robust, and stems from earlier work on a mechanistic/statistical model proposed by the NRC. From the independent reviews performed on the NRC proposed correlation, the evaluations of mechanistic understanding and statistical testing were combined to assess the most appropriate form for a mean correlation model. The process of evaluating and reducing the number of fitting parameters was not a simple decision. Engineering judgment, through the development of gating criteria and value/magnitude considerations, led to the development of the proposed correlation. This paper discusses the proposed embrittlement correlation and its mechanistic/statistical bases.
Author : Lendell E. Steele
Publisher : ASTM International
ISBN 13 :
Total Pages : 320 pages
Book Rating : 4.3/5 (91 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 1986 with total page 320 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 : PN. Randall
Publisher :
ISBN 13 :
Total Pages : 12 pages
Book Rating : 4.:/5 (125 download)
Download or read book Overview of U.S. Research and Regulatory Activities on Neutron Radiation Embrittlement of Pressure Vessel Steel written by PN. Randall and published by . This book was released on 1989 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper is in several parts: the first presents an overview of research activities sponsored by the U.S. Nuclear Regulatory Commission (NRC) on neutron irradiation embrittlement of pressure vessel steels. A series of irradiation experiments have evaluated effects of chemistry on the fracture toughness properties of submerged arc welds representing current nuclear vessel fabrication practices and provide data to validate ASME Code practices. A correlation between Charpy energy and fracture toughness is being studied as is a program on radiation sensitivity to define the role of dose rate and to study the effects of postirradiation heat treatment (annealing). The development of a comprehensive data base for radiation embrittlement data has been initiated and is being applied in a correlation of reactor surveillance data with test reactor data. A comprehensive dosimetry effort has produced validated standard methods for calculating and measuring neutron flux and fluence parameters and the correlation of these parameters to embrittlement of pressure vessel steels in light water reactors. Our knowledge of radiation damage to reactor vessels has also been greatly increased in recent years by the accumulation of power reactor surveillance data and by better models and better analysis techniques applied to that data. Unfortunately, the results show that radiation damage is often more than previously predicted, using Revision 1 of NRC Regulatory Guide 1.99, and will result in more restrictive pressure temperature limits. The second part of this paper describes some of the system and operational impacts produced, which in turn lead to challenges to long-established safety margins. Finally, a number of outstanding issues which require further research are discussed, many of which will require better understanding of radiation damage mechanisms.
Download or read book Radiation embrittlement of nuclear reactor pressure vessel steels written by and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Hawthorne, JR.
Publisher :
ISBN 13 :
Total Pages : 16 pages
Book Rating : 4.:/5 (125 download)
Download or read book Status of Knowledge of Radiation Embrittlement in U.S. Reactor Pressure Vessel Steels written by Hawthorne, JR. and published by . This book was released on 1983 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: Advances in experimental research in the United States toward an improved understanding of property changes in steel by elevated temperature (~288°C) irradiation are summarized. Four areas of investigation are reviewed, including the confirmation and demonstration of guidelines for radiation-resistant steels, the isolation of metallurgical factors contributing to variable radiation embrittlement sensitivity, the qualification of in situ heat treatments for periodic vessel embrittlement relief, and the correlation of notch ductility and fracture toughness changes with irradiation. Overall, the current state of the art provides both a high capability for tailoring steels for radiation service in new vessel construction and a promising method for controlling radiation embrittlement buildup in existing vessel construction.
Download or read book Physically Based Regression Correlations of Embrittlement Data from Reactor Pressure Vessel Surveillance Programs written by and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : R. G. Berggreen
Publisher :
ISBN 13 :
Total Pages : 19 pages
Book Rating : 4.:/5 (125 download)
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.
Download or read book Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels ; 2 written by and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
