Fracture Toughness Characterization of Japanese Reactor Pressure Vessel Steels PDF Download

Author: F. J. Loss
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Author: F. J. Loss
Publisher:
ISBN:
Category :
Languages : en
Pages : 38

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This report describes progress in a cooperative research program between the Electric Power Research Institute (EPRI) and NRL on the fracture toughness of steels for nuclear reactor pressure vessels. For its contribution EPRI furnished a major protion of the materials and test specimens for the study by NRL. The program is also being conducted in collaboration with the Nuclear Regulatory Commission (NRC), Office of Nuclear Regulatory Research, and the Office of Naval Research. Related NRC sponsored work of broader scope is underway at NRL. A portion of the NRC work pertaining to the fracture toughness of nuclear pressure boundary materials is also reported here because of its relevance to the subject effort. The principal objectives of this program are: (1) to characterize the dynamic fracture initiation toughness K sub Id of three heats of LWR pressure vessel steel, (2) to develop experimental and analytical techniques for the interpretation and analysis of notched, three-point bend specimen behavior under impact loading, and (3) to assess the validity of plane strain K sub Id values as projected from the elastic plastic (J integral) analysis of smaller specimens. The present report describes progress in the dynamic toughness assessment of program materials by means of 1-in. (25mm) bend and precracked Charpy-V specimens. Also described is a one-dimensional, theoretical characterization of the forces and bending moments developed during impact of a notched beam. (Author).

Author: DE. McCabe
Publisher:
ISBN:
Category : Fracture mechanics
Languages : en
Pages : 17

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In this study, precracked Charpy V-notch (PCVN) specimens were used to characterize the fracture toughness of unirradiated and irradiated reactor pressure vessel steels in the transition region by means of three-point static bending. Fracture toughness at cleavage instability was calculated in terms of elastic-plastic KJc values. A statistical size correction based upon weakest-link theory was performed. The concept of a master curve was applied to analyze fracture toughness properties. Initially, size-corrected PCVN data from A 533 grade B steel, designated HSST Plate 02, were used to position the master curve and a 5% tolerance bound for KJc data. By converting PCVN data to 1T compact specimen equivalent KJc data, the same master curve and 5% tolerance bound curve were plotted against the Electric Power Research Institute valid linear-elastic KIc database and the ASME lower bound KIc curve. Comparison shows that the master curve positioned by testing several PCVN specimens describes very well the massive fracture toughness database of large specimens. These results give strong support to the validity of KJc. with respect to KIc in general and to the applicability of PCVN specimens to measure fracture toughness of reactor vessel steels in particular. Finally, irradiated PCVN specimens of other materials were tested, and the results are compared to compact specimen data. The current results show that PCVNs demonstrate very good capacity for fracture toughness characterization of reactor pressure vessel steels. It provides an opportunity for direct measurement of fracture toughness of irradiated materials by means of precracking and testing Charpy specimens from surveillance capsules. However, size limits based on constraint theory restrict the operational test temperature range for KJc data from PCVN specimens.

Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 65

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Author: A. L. Hiser
Publisher:
ISBN: 9780160178924
Category : Metals
Languages : en
Pages : 193

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Author: Toshihiro Hanamura
Publisher: Springer
ISBN: 4431544992
Category : Technology & Engineering
Languages : en
Pages : 71

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In this book, advanced steel technologies mainly developed at the National Institute for Materials Science (NIMS), Japan, for structure control, mechanical properties, and the related mechanisms are introduced and discussed. NIMS has long worked on developing advanced steel techniques, namely, producing advanced steels by using only simple alloying elements such as carbon, manganese, and silicon, and also by utilizing steel scrap. The hope is that this approach will lead to a technology of a so-called steel-to-steel recycling process, with the ultimate goal of a recycling process such as an automotive-steel-to-automotive-steel recycling process to take the place of the current cascade-type recycling system. The main idea is to utilize ultra-grain refining structures and hetero structures as well as martensite structures. In particular, the focus of this book is on tensile strength and toughness of advanced steels from both the fundamental and engineering points of view. Fundamentally, a unique approach to analysis is taken, based on fracture surface energy as effective grain size is employed to better understand the mechanism of property improvement. From the engineering point of view, in fracture toughness such factors as crack tip opening displacement (CTOD) of advanced steels are evaluated in comparison with those of conventional steels.

Author: M. Suzuki
Publisher:
ISBN:
Category : Fracture toughness
Languages : en
Pages : 18

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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.

Author: Frank J. Loss
Publisher:
ISBN:
Category :
Languages : en
Pages : 32

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The principal objectives are: (a) to characterize the dynamic fracture toughness of three heats of nuclear pressure vessel steel, namely, 6-in. A302-B plate, 8-in. A533-B Class 1 plate, and 9-in. A508 Class 2 forging; and (b) to develop techniques for the interpretation and analysis of notched, three-point bend specimens tested under impact loading.

Author: Lendell E. Steele
Publisher: ASTM International
ISBN: 9780803100664
Category : Freshwater microbiology
Languages : en
Pages : 269

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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 18

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Book Description
In this study, precracked Charpy V-notch (PCVN) specimens were used to characterize the fracture toughness of unirradiated and irradiated reactor pressure vessel steels in the transition region by means of three-point static bending. Fracture toughness at cleavage instability was calculated in terms of elastic-plastic K{sub Jc} values. A statistical size correction based upon weakest-link theory was performed. The concept of a master curve was applied to analyze fracture toughness properties. Initially, size-corrected PCVN data from A 533 grade B steel, designated HSST Plate O2, were used to position the master curve and a 5% tolerance bound for K{sub Jc} data. By converting PCVN data to IT compact specimen equivalent K{sub Jc} data, the same master curve and 5% tolerance bound curve were plotted against the Electric Power Research Institute valid linear-elastic K{sub Jc} database and the ASME lower bound K{sub Ic} curve. Comparison shows that the master curve positioned by testing several PCVN specimens describes very well the massive fracture toughness database of large specimens. These results give strong support to the validity of K{sub Jc} with respect to K{sub Ic} in general and to the applicability of PCVN specimens to measure fracture toughness of reactor vessel steels in particular. Finally, irradiated PCVN specimens of other materials were tested, and the results are compared to compact specimen data. The current results show that PCVNs demonstrate very good capacity for fracture toughness characterization of reactor pressure vessel steels. It provides an opportunity for direct measurement of fracture toughness of irradiated materials by means of precracking and testing Charpy specimens from surveillance capsules. However, size limits based on constraint theory restrict the operational test temperature range for K{sub Jc} data from PCVN specimens. 13 refs., 8 figs., 1 tab.