Margins assessment for applying Master Curve data to high copper welds

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

Volumn 412, Issue , 2000, Pages 173-178

  Lott, Randy G ^a   Server, William L ^a   Kim, Charles C ^a   Tomes, Chuck A ^a  

^a NONE

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0040777052     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Article

References (16)

1. ASME Boiler and Pressure Vessel Code Case N-629, "Use of Fracture Toughness Test Data to Establish Reference Temperature for Pressure Retaining Materials, Section XI, Division 1," 1999.
2. ASME Boiler and Pressure Vessel Code Case N-631, "Use of Fracture Toughness Test Data to Establish Reference Temperature for Pressure Retaining Materials Other Than Bolting for Class 1 Vessels Section III, Division 1," 1999.
3. o, for Ferritic Steels in the Transition Range," 1998 Annual Book of ASTM Standards, Vol. 03.01.
4. W. Server et al., Application of Master Curve Fracture Toughness Methodology for Ferritic Steels, Revision 1 (PWRMRP-01), EPRI TR-108390-R1, May 1999.
5. PVRC Ad Hoc Group on Toughness Requirements, PVRC Recommendations on Toughness Requirements for Ferritic Steels, Welding Research Council Bulletin No. 175, August 1972.
6. T. U. Marston et al., Flaw Evaluation Procedures: Background and Application of ASME Section XI Appendix A, EPRI NP-719-SR, August 1978.
7. U.S. Nuclear Regulatory Commission Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials, May 1988.
8. Title10 Code of Federal Regulations, Part 50.61 (10 CFR 50.61), "Fracture Toughness Requirement for Protection Against Pressurized Thermal Shock Events," 1995.
9. T. M. Rosseel, Heavy Section Steel Irradiation Program, Semiannual Progress Report for October 1996 - March 1997, NUREG/CR-5991, 1997.
10. Draft NRC Staff Evaluation of Pressurized Thermal Shock, September 13, 1982.
11. Nuclear Regulatory Commission Safety Evaluation Report for the Palisades Reactor Vessel, 1992.
12. W. L. Server, C. Tomes, and C. Kim, Evaluation of the 1P3571 Weld Metal from the Surveillance Programs for Kewaunee and Maine Yankee, WCAP-15074, September 1998.
13. Nuclear Regulatory Commission Generic Letter 92-01, Revision 1 (GL 92-01), March 6, 1992.
14. Randy G. Lott, William L. Server, Charles C. Kim, and Timothy J. Griesbach, "Determination of Margins and Heat Adjustments for Master Curve Applications in RPV Integrity Analysis," this symposium.
15. Response to NRC Questions Regarding Margins To Be Used in Master Curve Integrity Assessment for the Kewaunee Nuclear Power Plant, EDRE-EMT-1467, Westinghouse Electric Company, LLC, January 2000.
16. E. D. Eason, J. E. Wright, and G. R. Odette, Improved Embrittlement Correlations for Reactor Pressure Vessel Steels, NUREG/CR-6551, MCS 97051, November 1998.