An investigation of shallow-flaw effects on the Master Curve indexing parameter (To) in RPV material

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP

Volumn 412, Issue , 2000, Pages 161-171

  McAfee, Wallace J ^a   Williams, Paul T ^a   Bass, B Richard ^a   McCabe, Donald E ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0012792319     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Article

References (19)

1. T. H. Theiss and D. K. M. Shum, "Experimental and Analytical Investigation of the Shallow-Flaw Effect in Reactor Pressure Vessels," USNRC Report NUREG/CR-5886 (ORNL/TM-12115), Oak Ridge National Laboratory, July 1992.
2. T. L. Dickson, W. J. McAfee, W. E. Pennell, and P. T. Williams, "Evaluation of Margins in the ASME Rules for Defining the P-T Curve for a RPV," pp. 47-72 in Proceedings of the Twenty-Sixth Water Reactor Safety Meeting, NUREG/CP-0166, Vol. 1, October 1998.
3. R. E. Link, Naval Surface Warfare Center, and J. A Joyce, U.S. Naval Academy, "Application of Fracture Toughness Scaling Models to the Ductile-to-Brittle Transition," USNRC Report NUREG/CR-6279, January 1996.
4. W. E. Pennell, B. R. Bass, J. W. Bryson, Jr., T. L. Dickson and J. G. Merkle, "Preliminary Assessment of the Effects of Biaxial Loading on Reactor Pressure Vessel Structural-Integrity-Assessment Technology," ORNL/NRC/LTR-94/31, Oak Ridge National Laboratory, August 1995.
5. T. L. Dickson, "Review of the Pressurized-Thermal Shock Screening Criteria for Embrittled Pressurized Water Reactor Pressure Vessels" ORNL/NRC/LTR-95/39, Oak Ridge National Laboratory, December 1995.
6. o, for Ferritic Steels in the Transition Range, American Society for Testing and Materials, West Conshohocken, PA, ASTM Standard Vol. 03.01, Section 3, Metals Test Methods and Analytical Procedures, (1998) 1068-1084.
7. o, for Ferritic Steels in the Transition Range," USNRC Report NUREG/CR-5504 (ORNL/TM-13631), Oak Ridge National Laboratory, November 1998.
8. ASME Boiler and Pressure Vessel Code, Code Case N-629 (in process), "Use of Fracture Toughness Test Data to Establish Reference Temperature for Pressure Retaining Materials of Section III, Division 1, Class 1," New York, 1998.
9. W. J. McAfee, B. R. Bass, P. T. Williams, and W. E. Pennell, "The Effect of Specimen Size on Fracture Toughness Values Obtained From Large-Scale Cruciform Specimens Under Biaxial Loading," ORNL/NRC/LTR-99/12, Oak Ridge National Laboratory, June 1999.
10. B. R. Bass, W. J. McAfee, P. T. Williams, and W. E. Pennell, "Evaluation of Constraint Methodologies Applied to a Shallow-Flaw Cruciform Bend Specimen Tested under Biaxial Loading Conditions," ASME/JSME Joint Pressure Vessels and Piping Conference, San Diego, California, July 26-30, 1998.
11. P. T. Williams, B. R. Bass, and W. J. McAfee, "Application of the Weibull Methodology to a Shallow-Flaw Cruciform Bend Specimen Tested under Biaxial Loading Conditions," 31st National Symposium on Fatigue and Fracture Mechanics, Volume STP 1389 (to be published), ASTM, Cleveland, OH, June 21-14, 1999.
12. o, for Ferritic Steels in the Transition Region," Engineering Fracture Mechanics 60(1), (1998) 19-36.
13. ASTM E 399-90, Standard Test Method for Plane-Strain Fracture Toughness of Metallic Materials, American Society for Testing and Materials, West Conshohocken, PA, ASTM Standard Vol. 03.01, Section 3, Metals Test Methods and Analytical Procedures. (1998) 413-443.
14. X. Gao and R. H. Dodds, Jr., "A Weibull Stress Model to Predict Cleavage Fracture in Plates Containing Surface Cracks," Fatigue & Fracture of Engineering Materials and Structures 22, (1999) 481-493.
15. K. Wallin, "Optimized Estimation of the Weibull Distribution Parameters," Research Report 604, Technical Research Center of Finland, Espoo, Finland, 1989.
16. X. Gao, C. Ruggieri, and R. H. Dodds, Jr., "Calibration of Weibull Stress Parameters using Fracture Toughness Data," International Journal of Fracture 92, (1998) 175-200.
17. th International Symposium, ASTM STP 1366, M. L. Hamilton, A. S. Kumar, S. T. Rosinski, and M. L. Grossbeck, Eds., American Society for Testing and Materials, West Conshohocken, PA, 2000..
18. T. H. Theiss and D. K. M. Shum, Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, "Experimental and Analytical Investigation of the Shallow-Flaw Effect in Reactor Pressure Vessel's," USNRC Report NUREG/CR-5886 (ORNL/TM-12115), July 1992.
19. R. K. Nanstad, M. A. Sokolov, and P. J. Mazoasz, Microstructural Banding and Biaxial Fracture Toughness Tests in a Specially Heat-Treated Reactor Pressure Vessel Steel," USNRC Report ORNL/NRC/LTR-00/01, Oak Ridge National Laboratory, in publication.