Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 14
Book Description
Several medium and high strength alloys, including AF1410, Inconel 718, PH 13-8 Mo stainless steel, and ASm(A723 high strength low alloy steel, have been heat treated to various strength and toughness levels and evaluated for correlations between fracture toughness and charpy impact energy. The correlations investigated included those by Roffe-Novak and Ault-Wald-Bertolo. previous work by Kapp and Underwood suggests that for A723 steel, the Rolfe-Novak correlation predicts the fracture toughness reasonably well. One potential limitation of their study was that the charpy impact energy was measured at -40 deg f, whereas the toughness was evaluated at room temperature. This study evaluates Charpy impact energy and toughness at both room temperature and at -40 deg F and considers both when utilizing these correlations. Results of this study indicate that the Rolfe-Novak correlation over-predicts the measured fracture toughness at room temperature, and tends to underpredict the measured fracture toughness at 40 deg F. The Ault-Wald-Bertolo correlation, in all but one instance, was a conservative estimate of the measured fracture toughness of the material at both room temperature and 40 deg F. Utilizing the results presented in this study, it is recommended that if a correlation is necessary for estimating the toughness of any of the materials, the Ault-Wald-Bertolo correlation will result in a conservative estimate of toughness. (MM).
Fracture Toughness Assessment of Present and Future Pressure Vessel Materials Based on Charpy Impact Energy and Yield Strength
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 14
Book Description
Several medium and high strength alloys, including AF1410, Inconel 718, PH 13-8 Mo stainless steel, and ASm(A723 high strength low alloy steel, have been heat treated to various strength and toughness levels and evaluated for correlations between fracture toughness and charpy impact energy. The correlations investigated included those by Roffe-Novak and Ault-Wald-Bertolo. previous work by Kapp and Underwood suggests that for A723 steel, the Rolfe-Novak correlation predicts the fracture toughness reasonably well. One potential limitation of their study was that the charpy impact energy was measured at -40 deg f, whereas the toughness was evaluated at room temperature. This study evaluates Charpy impact energy and toughness at both room temperature and at -40 deg F and considers both when utilizing these correlations. Results of this study indicate that the Rolfe-Novak correlation over-predicts the measured fracture toughness at room temperature, and tends to underpredict the measured fracture toughness at 40 deg F. The Ault-Wald-Bertolo correlation, in all but one instance, was a conservative estimate of the measured fracture toughness of the material at both room temperature and 40 deg F. Utilizing the results presented in this study, it is recommended that if a correlation is necessary for estimating the toughness of any of the materials, the Ault-Wald-Bertolo correlation will result in a conservative estimate of toughness. (MM).
Publisher:
ISBN:
Category :
Languages : en
Pages : 14
Book Description
Several medium and high strength alloys, including AF1410, Inconel 718, PH 13-8 Mo stainless steel, and ASm(A723 high strength low alloy steel, have been heat treated to various strength and toughness levels and evaluated for correlations between fracture toughness and charpy impact energy. The correlations investigated included those by Roffe-Novak and Ault-Wald-Bertolo. previous work by Kapp and Underwood suggests that for A723 steel, the Rolfe-Novak correlation predicts the fracture toughness reasonably well. One potential limitation of their study was that the charpy impact energy was measured at -40 deg f, whereas the toughness was evaluated at room temperature. This study evaluates Charpy impact energy and toughness at both room temperature and at -40 deg F and considers both when utilizing these correlations. Results of this study indicate that the Rolfe-Novak correlation over-predicts the measured fracture toughness at room temperature, and tends to underpredict the measured fracture toughness at 40 deg F. The Ault-Wald-Bertolo correlation, in all but one instance, was a conservative estimate of the measured fracture toughness of the material at both room temperature and 40 deg F. Utilizing the results presented in this study, it is recommended that if a correlation is necessary for estimating the toughness of any of the materials, the Ault-Wald-Bertolo correlation will result in a conservative estimate of toughness. (MM).
Scientific and Technical Aerospace Reports
Government Reports Announcements & Index
Energy Research Abstracts
Reactor Dosimetry
Author: Harry Farrar
Publisher: ASTM International
ISBN: 0803118996
Category : Nuclear reactors
Languages : en
Pages : 854
Book Description
Proceedings of the 8th ASTM-Euratom Symposium, held in Vail, Colorado, Aug.-Sept. 1993, to provide a forum for experts to discuss their latest results under the broad theme of dosimetry for the correlation of radiation effects. Preceded by a summary of the keynote presentations and followed by summa
Publisher: ASTM International
ISBN: 0803118996
Category : Nuclear reactors
Languages : en
Pages : 854
Book Description
Proceedings of the 8th ASTM-Euratom Symposium, held in Vail, Colorado, Aug.-Sept. 1993, to provide a forum for experts to discuss their latest results under the broad theme of dosimetry for the correlation of radiation effects. Preceded by a summary of the keynote presentations and followed by summa
Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants
Author: Naoki Soneda
Publisher: Elsevier
ISBN: 0857096478
Category : Technology & Engineering
Languages : en
Pages : 437
Book Description
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
Publisher: Elsevier
ISBN: 0857096478
Category : Technology & Engineering
Languages : en
Pages : 437
Book Description
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
Nuclear Science Abstracts
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 618
Book Description
NSA is a comprehensive collection of international nuclear science and technology literature for the period 1948 through 1976, pre-dating the prestigious INIS database, which began in 1970. NSA existed as a printed product (Volumes 1-33) initially, created by DOE's predecessor, the U.S. Atomic Energy Commission (AEC). NSA includes citations to scientific and technical reports from the AEC, the U.S. Energy Research and Development Administration and its contractors, plus other agencies and international organizations, universities, and industrial and research organizations. References to books, conference proceedings, papers, patents, dissertations, engineering drawings, and journal articles from worldwide sources are also included. Abstracts and full text are provided if available.
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 618
Book Description
NSA is a comprehensive collection of international nuclear science and technology literature for the period 1948 through 1976, pre-dating the prestigious INIS database, which began in 1970. NSA existed as a printed product (Volumes 1-33) initially, created by DOE's predecessor, the U.S. Atomic Energy Commission (AEC). NSA includes citations to scientific and technical reports from the AEC, the U.S. Energy Research and Development Administration and its contractors, plus other agencies and international organizations, universities, and industrial and research organizations. References to books, conference proceedings, papers, patents, dissertations, engineering drawings, and journal articles from worldwide sources are also included. Abstracts and full text are provided if available.
Prediction of Fracture Toughness KIc of 21⁄4Cr-1Mo Pressure Steels from Charpy V-Notch Test Results
Author: T. Iwadate
Publisher:
ISBN:
Category : Crack propagation
Languages : en
Pages : 14
Book Description
The validity of the Barsom, Rolfe, and Novak correlation between Charpy energy, yield strength, and KIc in the upper-shelf region has been confirmed for 21⁄4Cr-1Mo pressure vessel steels. The relationship between the excess temperature and KIc/KIc-upper shelf has also been developed. Based on these relationships, KIc transition curves may be predicted from Charpy V-notch test results of 21⁄4Cr-1Mo pressure vessel steels.
Publisher:
ISBN:
Category : Crack propagation
Languages : en
Pages : 14
Book Description
The validity of the Barsom, Rolfe, and Novak correlation between Charpy energy, yield strength, and KIc in the upper-shelf region has been confirmed for 21⁄4Cr-1Mo pressure vessel steels. The relationship between the excess temperature and KIc/KIc-upper shelf has also been developed. Based on these relationships, KIc transition curves may be predicted from Charpy V-notch test results of 21⁄4Cr-1Mo pressure vessel steels.
Status of USA Nuclear Reactor Pressure Vessel Surveillance for Radiation Effects
Author: Lendell E. Steele
Publisher: ASTM International
ISBN: 9780803102293
Category : Technology & Engineering
Languages : en
Pages : 290
Book Description
Publisher: ASTM International
ISBN: 9780803102293
Category : Technology & Engineering
Languages : en
Pages : 290
Book Description