Determination of margins and heat adjustments for Master Curve applications in RPV integrity analysis

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

Volumn 412, Issue , 2000, Pages 179-185

  Lott, Randy G ^a   Server, William L ^a   Kim, Charles C ^a   Griesbach, Timothy J ^a  

^a NONE

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0038998660     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Article

References (15)

1. R.G. Lott, W.L. Server, C.C. Kim, and C.A. Tomes, "Margins Assessment for Applying Master Curve Data to High Copper Welds, this symposium.
2. 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.
3. 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.
4. Nuclear Regulatory Commission Generic Letter 92-01, Revision 1 (GL 92-01), March 6, 1992.
5. o, for Ferritic Steels in the Transition Range," 1998 Annual Book of ASTM Standards, Vol. 03.01.
6. J. T. Buswell and R. B. Jones, "The Modeling of Radiation Hardening and Embrittlement in Magnox Mild Steel Submerged-Arc Welds," ASTM STP 1175, 1993, p. 424.
7. 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.
8. U.S. Nuclear Regulatory Commission Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials, May 1988.
9. Title10 Code of Federal Regulations, Part 50.61 (10 CFR 50.61), "Fracture Toughness Requirement for Protection Against Pressurized Thermal Shock Events," 1995.
10. Nuclear Regulatory Commission Generic Letter 92-01, Revision 1 (GL 92-01), March 6, 1992.
11. Nuclear Regulatory Commission Safety Evaluation Report for the Palisades Reactor Vessel, 1992.
12. 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.
13. 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.
14. R. G. Lott, M. T. Kirk, and C. C. Kim, Master Curve Strategies for RPV Assessment, WCAP-15075, September 1998.
15. 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.