Mechanical Properties Database of Reactor Pressure Vessel Steels Related to Fracture Toughness Evaluation PDF Download

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

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Author: American Society of Mechanical Engineers. Winter Annual Meeting
Publisher:
ISBN:
Category : Fracture mechanics
Languages : en
Pages : 114

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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: J. E. Campbell
Publisher:
ISBN:
Category : Steel, High strength
Languages : en
Pages : 22

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The Memorandum discusses the current situation on the inclusion of fracture-toughness testing requirements in specifications for high-strength steels used for military applications. The Memorandum was prepared at the request of The Technical Cooperation Program (TTCP), and contains information from Canadian and British members of that program, as well as U.S. information. Military applications discussed include missile motor cases, aircraft landing gear, gun tubes, armor plate, and hydrofoils. (Author).

Author: H. Hein
Publisher:
ISBN:
Category : Crack arrest
Languages : en
Pages : 24

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Pre-irradiated original reactor pressure vessel (RPV) materials covering all four German pressurized water reactors (PWR) construction lines were tested in the Crack Initiation and Arrest of Irradiated Steel Materials program to create a database of fracture toughness and arrest values for neutron fluences beyond the end of life range. The new database comprises data from both unirradiated and irradiated RPV base and weld materials generated by tensile, Charpy-V impact, fracture toughness KJc, and crack arrest KIa tests. The test matrix consists of materials with optimized chemical composition and with high Copper or high Nickel content, respectively. Based on the generated and already existing data the RTNDT and the RTT0 (Master Curve) concepts are applied with specific view on reference temperatures, transition temperature shifts, and on possible correlations between the criteria used in both concepts. In this context the consequences of some influencing factors like type and chemical composition of the RPV steel, its manufacturing conditions, and the specimen type and size on the reference temperatures are discussed. Moreover, the test results are assessed with respect to the American Society of Mechanical Engineers (ASME) code and German Nuclear Safety Standards Commission safety standards. The crack arrest characteristics for these typical RPV materials are also determined in a twofold way by testing Compact Crack Arrest specimens and by evaluation of instrumented Charpy-V impact test data. The available results made a good point that crack arrest is a reliable phenomenon that doubtless exists. It is also shown that the obtained KIa data can be enveloped by applying the ASME KIc lower bound curve indexed by different reference temperatures. Finally, the results show that the used RPV materials are well designed in terms of material behavior under irradiated conditions and that optimized manufacture specifications are of great benefit particularly after long operation times.

Author: Richard Swift McClaughry
Publisher:
ISBN:
Category :
Languages : en
Pages : 214

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Author: F. Nogata
Publisher:
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Category : Cleavage fracture
Languages : en
Pages : 9

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A new evaluation procedure for the critical fracture toughness (KIc, KId) from Charpy-V impact absorbed energy is presented. The strain-rate/temperature effect on the cleavage-controlled fracture toughness transition is first explained by applying the concept of a stress-dependent rate process for fracture initiation. The expression described in terms of the Charpy-V energy ratio, Cv-us/Cv, for fracture toughness under a constant strain rate is newly derived. The feasibility of the new procedure for evaluating the irradiation embrittlement of reactor pressure vessel steel, such as SA533B-1, is here verified utilizing the data for both unirradiated and irradiated materials in the literature. Another method for the determination of coefficients in the new expression from the Cv-fitting curve is also presented.

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:
Publisher:
ISBN:
Category : Nuclear pressure vessels
Languages : en
Pages : 67

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Author: Satoshi Nishijima
Publisher: ASTM International
ISBN: 0803124198
Category : Information storage and retrieval systems
Languages : en
Pages : 286

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