Analytical modeling of the effect of crack depth, specimen size, and biaxial stress on the fracture toughness of reactor vessel steels

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Description

Fracture, toughness values for A533-B reactor pressure vessel (RPV) steel obtained from test programs at Oak Ridge National Laboratory (ORNL) and University of Kansas (KU) are interpreted using the J-A{sub 2} analytical model. The analytical model is based on the critical stress concept and takes into consideration the constraint effect using the second parameter A{sub 2} in addition to the generally accepted first parameter J which represents the loading level. It is demonstrated that with the constraint level included in the model effects of crack depth (shallow vs deep), specimen size (small vs. large), and loading type (uniaxial vs biaxial) ... continued below

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19 p.

Creation Information

Chao, Yuh-Jin & Lam, Poh-Sang February 1, 1995.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 54 times . More information about this report can be viewed below.

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  • Chao, Yuh-Jin Univ. of South Carolina, Columbia, SC (United States). Dept. of Mechanical Engineering
  • Lam, Poh-Sang Westinghouse Savannah River Co., Aiken, SC (United States)

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Description

Fracture, toughness values for A533-B reactor pressure vessel (RPV) steel obtained from test programs at Oak Ridge National Laboratory (ORNL) and University of Kansas (KU) are interpreted using the J-A{sub 2} analytical model. The analytical model is based on the critical stress concept and takes into consideration the constraint effect using the second parameter A{sub 2} in addition to the generally accepted first parameter J which represents the loading level. It is demonstrated that with the constraint level included in the model effects of crack depth (shallow vs deep), specimen size (small vs. large), and loading type (uniaxial vs biaxial) on the fracture toughness from the test programs can be interpreted and predicted.

Physical Description

19 p.

Notes

INIS; OSTI as DE95005886

Source

  • Joint American Society of Mechanical Engineers (ASME)/Japan Society of Mechanical Engineers (JSME) pressure vessels and piping conference, Honolulu, HI (United States), 23-27 Jul 1995

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  • Other: DE95005886
  • Report No.: WSRC-MS--94-0463
  • Report No.: CONF-950740--5
  • Grant Number: AC09-89SR18035
  • DOI: 10.2172/46556 | External Link
  • Office of Scientific & Technical Information Report Number: 46556
  • Archival Resource Key: ark:/67531/metadc674210

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • February 1, 1995

Added to The UNT Digital Library

  • July 25, 2015, 2:21 a.m.

Description Last Updated

  • Feb. 9, 2016, 4:39 p.m.

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Chao, Yuh-Jin & Lam, Poh-Sang. Analytical modeling of the effect of crack depth, specimen size, and biaxial stress on the fracture toughness of reactor vessel steels, report, February 1, 1995; Aiken, South Carolina. (digital.library.unt.edu/ark:/67531/metadc674210/: accessed October 22, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.