Initial reference temperatures and irradiation trend curves for use with rtto, a preliminary assessment

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

Volumn 393, Issue , 1999, Pages 71-78

  Kirk, Mark ^a   Lott, Randy ^a   Server, William ^b   Rosinski, Stan ^c  

^a WESTINGHOUSE ELECTRIC COMPANY   (United States)

^b ATI Consulting   (United States)

^c ELECTRIC POWER RESEARCH INSTITUTE   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

CRACK PROPAGATION; FRACTURE TOUGHNESS; IRRADIATION; PRESSURE VESSEL CODES; STEEL STRUCTURES;

MASTER CURVE METHOD; PRECRACKED CHARPY SPECIMENS;

PRESSURE VESSELS;

EID: 0033336641     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Article

References (27)

1. ASME N629. ASME Code Case N-629, "Use of Fracture Toughness Test Data to Establish Reference Temperature for Pressure Retaining Materials for Section XI."
2. ASTM E23-96. "Standard test Methods for Notched Bar Impact Testing of Metallic Materials," ASTM, 1998.
3. ASTM E2Q8-95a. "Standard Test Method for Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperature of Ferritic Steels," ASTM 1998.
4. ASTM E1921-97. "Test Method for Determination of Reference Temperature, T0, for Ferritic Steels in the Transition Range," ASTM, 1998.
5. ASTM E185-94. "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," ASTM, 1998.
6. Bvrne 1999. "Summary of Master Curve Test Results," private communication.
7. Eason 1998. Eason, E.D., Wright, J.E., and Odette, G.R., "Improved Embrittlement Correlations for Reactor Pressure Vessel Steels," NUREG/CR-6551,1998.
8. EPRI 1998. "Application of Master Curve Fracture Toughness Methodology for Ferritic Steels," EPRI-TR-108390, 1998.
9. Hawthorne, et al. 1984. Hawthorne, J.R., Menke, B.H., Hiser, A.L., "Notch Ductility and Fracture Toughness Degradation of A302-B and A533-B Reference Plates from PSF Simulated Surveillance and Through-Wall Irradiation Capsules," NUREG/CR-3295 (Vol. 1), USNRC, 1984.
10. Hawthorne and Hiser 1988. Hawthorne, J.R., Hiser, A.L., "Experimental Assessments of Gundremmingen RPV Archive Material for Fluence Rate Effects Studies," NUREG-CR/5201, US-NRC, 1988.
11. Hawthorne and Hiser 1990(a). Hawthorne, J.R., Hiser, A.L., "Investigations of Irradiation-Anneal-Reirradiation (IAR) Properties Trends of RPV Welds: Phase 2 Final Report," NUREG-CR/5492, US-NRC, 1990.
12. Hawthorne and Hiser 1990(b). Hawthorne, J.R., Hiser, A.L., "Influence of Fluence Rate on Radiation-Induced Mechanical Property Changes in RPV Steels," NUREG/CR-5493, US-NRC, 1990.
13. Hawthorne, et al. 1992. Hawthorne, J.R., Menke, B.H., Loss, F.J., Watson, H.E., Hiser, A.L., and Gray, R.A., "Evaluation and Prediction of Neutron Embrittlement in Reactor Pressure Vessel Materials," EPRI NP-2782, EPRI, 1992
14. Hiser 1989. Hiser, A.L., "Post-Irradiation Fracture Toughness Characterization of Four Lab-Melt Plates," NUREG/CR-5216 (Rev. 1), US-NRC, 1989.
15. Kirk 1998. Kirk, M., Lott, R., Kirn, C., and Server, W., "Empirical Validation Of The Master Curve For Irradiated And Unirradiated Reactor Pressure Vessel Steels," Presented at the 1998 ASME/JSME Pressure Vessel and Piping Symposium, July 26-30,1998, San Diego, California, USA.
16. Lott 1999. Lott, R., Kirk, M., Kirn, C., Server, W., Tomes, C., Williams, J., "Application of Master Curve Technology
17. to Estimation of End Of License Adjusted Reference Temperature for a Nuclear Power Plant," Presented at the 1999 ASME Pressure Vessel and Piping Symposium, August 2-5,1999, Boston, Massachusetts, USA.
18. McGowan. et al. 1988. McGowan, et al., "Characterization of Irradiated Current-Practice Welds and A533 Grade B Class 1 Plate for Nuclear Pressure Vessel Service, NUREG/CR-4880, U.S. Nuclear Regulatory Commission, 1988.
19. Merkle 1998. Merkle, J.G., Wallin, K, McCabe, D.E., "Technical Basis for an ASTM Standard for Determining the Reference Temperature, To, for Ferritic Steels in the Transition Range," NUREG/CR-5504,1998.
20. th Volume, ASTM STP-1360, K. Jerina and P. Paris, Eds., American Society for Testing and Materials, 1998.
21. Randall 1987. Randall, P.N., "Basis for Revision 2 of the U.S. Nuclear Regulatory Commission's Regulatory Guide 1.99," Radiation Embrittlement in Nuclear Pressure Vessel Steels: An International Review (Second Volume), ASTM STP-909, L.E. Steele, Ed., 1987.
22. RG1.99. Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials, U.S. Nuclear Regulatory Commission, May 1988.
23. SECY-82-465. SECY-82-465, Enclosure A, "NRC Staff Evaluation of Pressurized Thermal Shock," November 1982.
24. Jc and Charpy Impact Toughness for Reactor Pressure Vessel Steels," ASTM STP-1325, American Society of testing and Materials, 1996.
25. Wallin 1984. Wallin, Saario, and Törrönen, "Statistical Model for Carbide Induced Brittle Fracture in Steel," Metal Science, 18, pp. 13-16,1984.
26. Wallin 1993. Wallin, K, "Irradiation Damage Effects on the Fracture Toughness Transition Curve Shape for Reactor Vessel Steels," Int. J. Pres. Ves. & Piping, 55, pp. 61-79, 1993.
27. Wallin 1995. Wallin, K, "Re-Evaluation of the TSE Results Based on the Statistical Size Effect," VTT Manufacturing Technology, 1995.