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Title: Ductile fracture toughness of modified A 302 grade B plate materials. Volume 2

Abstract

The objective of this work was to develop ductile fracture toughness data in the form of J-R curves for modified A 302 grade B plate materials typical of those used in fabricating reactor pressure vessels. A previous experimental study at Materials Engineering Associates (MEA) on one particular heat of A 302 grade B plate showed decreasing J-R curves with increased specimen thickness. This characteristic has not been observed in numerous tests made on the more recent production materials of A 533 grade B and A 508 class 2 pressure vessel steels. It was unknown if the departure from norm for the MEA material was a generic characteristic for all heats of A 302 grade B steels or just unique to that one particular plate. Seven heats of modified A 302 grade B steel and one heat of vintage A 533 grade B steel were provided to this project by the General Electric Company of San Jose, California. All plates were tested for chemical content, tensile properties, Charpy transition temperature curves, drop-weight nil-ductility transition (NDT) temperature, and J-R curves. Tensile tests were made in the three principal orientations and at four temperatures, ranging from room temperature to 550{degrees}F (288{degrees}C). Charpy V-notchmore » transition temperature curves were obtained in longitudinal, transverse, and short transverse orientations. J-R curves were made using four specimen sizes (1/2T, IT, 2T, and 4T). None of the seven heats of modified A 302 grade showed size effects of any consequence on the J-R curve behavior. Crack orientation effects were present, but none were severe enough to be reported as atypical. A test temperature increase from 180 to 550{degrees}F (82 to 288{degrees}C) produced the usual loss in J-R curve fracture toughness. Generic J-R curves and mathematical curve fits to the same were generated to represent each heat of material. This volume is a compilation of all data developed.« less

Authors:
; ;
Publication Date:
Research Org.:
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering Technology; Oak Ridge National Lab., TN (United States)
Sponsoring Org.:
Nuclear Regulatory Commission, Washington, DC (United States)
OSTI Identifier:
453788
Report Number(s):
NUREG/CR-6426-Vol.2; ORNL-6892/V2
ON: TI97003758; TRN: 97:006784
DOE Contract Number:
AC05-96OR22464
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Feb 1997
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; STEEL-ASTM-A302; FRACTURE PROPERTIES; DUCTILE-BRITTLE TRANSITIONS; STEEL-ASTM-A533-B; PRESSURE VESSELS; MATERIALS TESTING; COMPILED DATA

Citation Formats

McCabe, D.E., Manneschmidt, E.T., and Swain, R.L.. Ductile fracture toughness of modified A 302 grade B plate materials. Volume 2. United States: N. p., 1997. Web. doi:10.2172/453788.
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McCabe, D.E., Manneschmidt, E.T., & Swain, R.L.. Ductile fracture toughness of modified A 302 grade B plate materials. Volume 2. United States. doi:10.2172/453788.
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McCabe, D.E., Manneschmidt, E.T., and Swain, R.L.. Sat . "Ductile fracture toughness of modified A 302 grade B plate materials. Volume 2". United States. doi:10.2172/453788. https://www.osti.gov/servlets/purl/453788.
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@article{osti_453788,
title = {Ductile fracture toughness of modified A 302 grade B plate materials. Volume 2},
author = {McCabe, D.E. and Manneschmidt, E.T. and Swain, R.L.},
abstractNote = {The objective of this work was to develop ductile fracture toughness data in the form of J-R curves for modified A 302 grade B plate materials typical of those used in fabricating reactor pressure vessels. A previous experimental study at Materials Engineering Associates (MEA) on one particular heat of A 302 grade B plate showed decreasing J-R curves with increased specimen thickness. This characteristic has not been observed in numerous tests made on the more recent production materials of A 533 grade B and A 508 class 2 pressure vessel steels. It was unknown if the departure from norm for the MEA material was a generic characteristic for all heats of A 302 grade B steels or just unique to that one particular plate. Seven heats of modified A 302 grade B steel and one heat of vintage A 533 grade B steel were provided to this project by the General Electric Company of San Jose, California. All plates were tested for chemical content, tensile properties, Charpy transition temperature curves, drop-weight nil-ductility transition (NDT) temperature, and J-R curves. Tensile tests were made in the three principal orientations and at four temperatures, ranging from room temperature to 550{degrees}F (288{degrees}C). Charpy V-notch transition temperature curves were obtained in longitudinal, transverse, and short transverse orientations. J-R curves were made using four specimen sizes (1/2T, IT, 2T, and 4T). None of the seven heats of modified A 302 grade showed size effects of any consequence on the J-R curve behavior. Crack orientation effects were present, but none were severe enough to be reported as atypical. A test temperature increase from 180 to 550{degrees}F (82 to 288{degrees}C) produced the usual loss in J-R curve fracture toughness. Generic J-R curves and mathematical curve fits to the same were generated to represent each heat of material. This volume is a compilation of all data developed.},
doi = {10.2172/453788},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat Feb 01 00:00:00 EST 1997},
month = {Sat Feb 01 00:00:00 EST 1997}
}
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DOI:  10.2172/453788
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  • ; ;
    The goal of this work was to develop ductile fracture toughness data in the form of J-R curves for modified A302 grade B plate materials typical of those used in reactor pressure vessels. A previous experimental study on one heat of A302 grade B plate showed decreasing J-R curves with increased specimen thickness. This characteristic has not been observed in tests made on recent production materials of A533 grade B and A508 class 2 pressure vessel steels. It was unknown if the departure from norm for the material was a generic characteristic for all heats of A302 grade B steelsmore » or unique to that particular plate. Seven heats of modified A302 grade B steel and one heat of vintage A533 grade B steel were tested for chemical content, tensile properties, Charpy transition temperature curves, drop-weight nil-ductility transition (NDT) temperature, and J-R curves. Tensile tests were made in the three principal orientations and at four temperatures, ranging from room temperature to 550F. Charpy V-notch transition temperature curves were obtained in longitudinal, transverse, and short transverse orientations. J-R curves were made using four specimen sizes (1/2T, 1T, 2T, and 4T). The fracture mechanics-based evaluation method covered three test orientations and three test temperatures (80, 400, and 550F). However, the coverage of these variables was contingent upon the amount of material provided. Drop-weight NDT temperature was determined for the T-L orientation only. None of the heats of modified A302 grade B showed size effects of any consequence on the J-R curve behavior. Crack orientation effects were present, but none were severe enough to be reported as atypical. A test temperature increase from 180 to 550F produced the usual loss in J-R curve fracture toughness. Generic J-R curves and curve fits were generated to represent each heat of material. This volume deals with the evaluation of data and the discussion of technical findings. 8 refs., 18 figs., 8 tabs.« less

  • ; ; ; ...
    As a result of the Heavy Section Steel Technology Program (HSST), sponsored by the Nuclear Regulatory Commission, Westinghouse Electric Corporation conducted dynamic fracture toughness tests on irradiated HSST Plate 02 and submerged arc weldment material. Testing performed at the Westinghouse Research and Development Laboratory in Pittsburgh, Pennsylvania, included 0.394T compact tension, 1.9T compact tension, and 4T compact tension specimens. This data showed that, in the transition region, dynamic test procedures resulted in lower (compared to static) fracture toughness results, and that weak direction (WR) oriented specimen data were lower than the strong direction (RW) oriented specimen results. Irradiated lower-bound fracturemore » toughness results of the HSST Program material were well above the adjusted ASME Section III K/sub IR/ curve. An irradiated and nonirradiated 4T-CT specimen was tested during a fracture toughness test as a preliminary study to determine the effect of irradiation on the acoustic emission-stress intensity factor relation in pressure vessel grade steel. The results indicated higher levels of acoustic emission activity from the irradiated sample as compared to the unirradiated one at a given stress intensity factor (K) level.« less

  • ; ; ; ...
    The Appendices presented in Volume II, Parts I and II of 'Fracture Toughness Data for Ferritic Nuclear Pressure Vessel Materials,' represent the detailed analysis of approximately 20,000 experimental test results. Due to the large quantity of data, Volume I was written to familiarize the reader with the overall program and objectives, to present the analytical tools developed for statistically analyzing the data, and to provide specific examples for the interpretation of the data in Volume II. Vol. I also contains the conclusions and recommendations reached after the data were analyzed. This volume discusses the following materials: A533 grade B, classmore » 1 steel; A508 class 2 forging steel; A540 grade B-23 and B-24 bolting steels; A302 grade B steel.« less

  • ; ;
    Mechanical properties data have been developed for two of the materials: the ASTM A302-B correlation monitor reference plate and the A533-B plate No. 03 from the NRC's Heavy Section Steel Technology Program. These results are presented together with an overview of specimen irradiation and testing procedures. Data comparisons are used to describe the observed toughness gradient produced by irradiation where fluences were typical of vessel end-of-life conditions. In addition, assessments are made of the relative irradiation effect at surveillance capsule vs. through-wall locations and the correspondence of Charpy-V vs. fracture toughness test methods in their independent descriptions of radiation-induced embrittlement.more » Irradiation in the simulated surveillance capsule location was found to reproduce reasonably well the irradiation effect to vessel inner surface and quarter wall thickness positions. As expected, the adjustment of the ASME lower bound (i.e., dynamic) K/sub IR/ toughness curve by the radiation induced elevation of the Charpy-V 41 J and the compact specimen 100 MPa ..sqrt..m temperatures was conservative when compared against the static toughness data. However, the temperature elevation of the C/sub v/ curve (41 J level) with irradiation frequently did not provide a conservative estimate of the temperature elevation defined by fracture toughness tests (100 MPa ..sqrt..m level). On the other hand, correction of the fracture toughness data for lack of test specimen constraint (..beta../sub Ic/-correction) results in transition temperature elevations less than the C/sub v/ 41 J elevations, in most cases. Overall, the toughness gradient observed between in-wall locations after irradiation was small for both materials; the difference between transition temperatures for wall surface vs. mid thickness locations was 31/sup 0/C or less, independent of the test method used. Candidate areas for future research investigation are discussed.« less