Fracture Probability Integral Applied to Reactor Vessel Life Estimate

[+] Author and Article Information
Shih-Jung Chang

Senior Research Staff, High Flux Isotope Reactor, Oak Ridge National Laboratory, Oak Ridge, TN 37831-6399 e-mail: sjc@ornl.gov

J. Pressure Vessel Technol 123(3), 346-354 (Feb 05, 2001) (9 pages) doi:10.1115/1.1376713 History: Received September 22, 2000; Revised February 05, 2001
Your Session has timed out. Please sign back in to continue.


Chang,  S. J., 1998, “Probability of Fracture and Life Extension Estimate of the High Flux Isotope Reactor Vessel,” ASME J. Pressure Vessel Technol., 120, pp. 209–296; also, 1997, ed., K. K. Panahi, ASME PVP-Vol. 355, pp. 207–214.
Chang, S. J., 1998, “Fracture Probability and Leak Before Break Analysis for the Cold Neutron Source Moderator Vessel,” eds., S. J. Chang and D. Brochard, ASME PVP-Vol. 366, pp. 35–44.
Chang,  S. J., 1994, “Probability of Fracture for HFIR Pressure Vessel Caused by Random Crack Size or by Random Toughness,” ASME J. Pressure Vessel Technol., 116, pp. 24–29.
Cheverton, R. D., Merkle, J. G., and Nanstat, R. K., 1988, “Evaluation of HFIR Pressure Vessel Integrity Considering Radiation Embrittlement,” ORNL/TM-10444, Oak Ridge National Laboratory, Oak Ridge, TN.
Cheverton, R. D., and Dickson, T. L., 1998, “HFIR Vessel Life Extension With Enlarged HB-2 and HB-4 Beam Tubes,” ORNL/TM-13698, Oak Ridge National Laboratory, Oak Ridge, TN.
Hirsch,  P. B., Roberts,  S. G., and Sanmuels,  J., 1988, “The Brittle-Ductile Transition in Silicon,” Proc. R. Soc. London, Ser. A, A421, pp. 25–53.
Chang,  S. J., and Ohr,  S. M., 1981, “Dislocation Free Zone Model of Fracture,” J. Appl. Phys., 52, pp. 7174–7181.
Gates,  R. A., 1983, “The Relationship Between Load Factors and Failure Probabilities Determined From a Full Elastic-Plastic Probability Fracture Mechanics Analysis,” Int. J. Pressure Vessels Piping, 13, pp. 155–167.
Wilson, R., Mitchell, B. J. and Ainsworth, R. A., 1996, “Relationship Between Conditional Failure Probabilities and Corresponding Reserve Factors Derived From R6 Failure Assessment Diagram,” ASME PVP-Vol. 323, pp. 401–404.
Remec,  I., Wang,  J. A., Kam,  F. B., and Farrel,  K., 1994, “Effect of Gamma Induced Displacements on HFIR Pressure Vessel Materials,” J. Nucl. Mater., 217, pp. 258–268.
Marshall, W., 1982, “An Assessment of the Integrity of PWR Pressure Vessels,” United Kingdom Atomic Energy Authority.


Grahic Jump Location
Probability of fracture, plane strain toughness and transition temperature shift: (a) region 1, and (b) region 3
Grahic Jump Location
Parametric study on the variation of the standard deviation of fracture toughness to fracture probability: (a) region 1, and (b) region 3
Grahic Jump Location
Parametric study on the variation of the transition temperature shift to fracture probability: (a) region 1, and (b) region 3
Grahic Jump Location
Numerical study to obtain the limiting probability of fracture (the simplistic probability of fracture) by decreasing the standard deviation of the fracture toughness




Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related Journal Articles
Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In