Fracture-safe operating criteria for commercial nuclear pressure vessels based on fracture analysis diagram procedures and Charpy-V energy trends are reappraised with respect to the effects of thick section mechanical constraint and low Charpy - V shelf energies resulting from neutron irradiation. Comparisons of the Charpy-V test with the more definitive dynamic tear test procedures indicate the former to be an acceptable means of assessing the fracture toughness of A533-B steel. The mechanical constraint associated with 12-in. thicknesses of this steel suggests the addition of 70 F (39 C) to the existing criterion requiring vessel operation above NDT + 60 F (33 C). Ratio analysis diagram procedures are shown to be useful in interpreting Charpy-V shelf level data obtained from vessel surveillance programs in terms of critical toughness levels relating to brittle fracture.
Skip Nav Destination
Article navigation
Research Papers
A Reassessment of Fracture-Safe Operating Criteria for Reactor Vessel Steels Based on Charpy-V Performance
F. J. Loss,
F. J. Loss
Metallurgy Division (Code 6390), Naval Research Laboratory, Washington, D. C.
Search for other works by this author on:
J. R. Hawthorne,
J. R. Hawthorne
Metallurgy Division (Code 6390), Naval Research Laboratory, Washington, D. C.
Search for other works by this author on:
C. Z. Serpan, Jr.
C. Z. Serpan, Jr.
Metallurgy Division (Code 6390), Naval Research Laboratory, Washington, D. C.
Search for other works by this author on:
F. J. Loss
Metallurgy Division (Code 6390), Naval Research Laboratory, Washington, D. C.
J. R. Hawthorne
Metallurgy Division (Code 6390), Naval Research Laboratory, Washington, D. C.
C. Z. Serpan, Jr.
Metallurgy Division (Code 6390), Naval Research Laboratory, Washington, D. C.
J. Basic Eng. Jun 1971, 93(2): 247-258 (12 pages)
Published Online: June 1, 1971
Article history
Received:
July 30, 1970
Online:
October 27, 2010
Citation
Loss, F. J., Hawthorne, J. R., and Serpan, C. Z., Jr. (June 1, 1971). "A Reassessment of Fracture-Safe Operating Criteria for Reactor Vessel Steels Based on Charpy-V Performance." ASME. J. Basic Eng. June 1971; 93(2): 247–258. https://doi.org/10.1115/1.3425221
Download citation file:
14
Views
Get Email Alerts
Cited By
Related Articles
Analysis of Radiation-Induced Embrittlement Gradients on Fracture Characteristics of Thick-Walled Pressure Vessel Steels
J. Eng. Ind (November,1971)
Heavy-Section Steel Technology and Irradiation Programs—Retrospective and Prospective Views
J. Pressure Vessel Technol (December,2010)
Industry Practice for the Neutron Irradiation Embrittlement of Reactor Pressure Vessels in Japan
J. Eng. Gas Turbines Power (October,2010)
Related Proceedings Papers
Related Chapters
Subsection NCA—General Requirements for Division 1 and Division 2
Companion Guide to the ASME Boiler & Pressure Vessel Code, Volume 1, Second Edition
Subsection NCA—General Requirements for Division 1 and Division 2
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 1, Third Edition
Radial Delayed Hydride Cracking in Irradiated Zircaloy-2 Cladding: Advanced Characterization Techniques
Zirconium in the Nuclear Industry: 20th International Symposium