Potential roles for the Master Curve in regulatory application

International Journal of Pressure Vessels and Piping

Volumn 78, Issue 2-3, 2001, Pages 111-123

  Kirk, M ^a   Mitchell, M ^a  

^a United States Nucl Reg Comm   (United States)

Author keywords

Master curve; Nuclear regulatory commission; Pressurized water reactors

Indexed keywords

FRACTURE MECHANICS; ROBUSTNESS (CONTROL SYSTEMS); STEEL;

MASTER CURVE PROCEDURES;

PRESSURE VESSELS;

NUCLEAR APPLICATION; POWER PLANT; REACTOR; WATER;

EID: 0035908024     PISSN: 03080161     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0308-0161(01)00034-5     Document Type: Article

References (45)

1. Fracture toughness requirements for protection against pressurized thermal shock events
2. Improved embrittlement correlations for reactor pressure vessel steels
3. Jc and charpy impact toughness for reactor pressure vessel steels
4. To. A preliminary assessment
5. o, for ferritic Steels in the transition range
6. NDT determination for some reactor vessel weld metals validated by fracture toughness data
7. Application of Master Curve technology to estimation of end of license adjusted reference temperature for a nuclear power plant
8. Margins assessment for applying Master Curve-data to high copper welds
9. Determination of margins and heat adjustments for Master Curve applications in RPV integrity analysis
10. Application of revised fracture toughness curves in pressure vessel integrity analysis
11. A micro-mechanical evaluation of the Master Curve
12. Dislocation mechanics basis and stress state dependency of the Master Curve
13. A physical basis for the Master Curve
14. Developing fracture assessment models for fusion reactor materials with small specimens
15. On the relationship between critical tensile stress and fracture stress in mild steels
16. A physical model of the Master Curve shape
17. o, for ferritic steels in the transition region
18. o reference temperature from precracked Charpy specimens
19. Bias and precision of to values determined using ASTM standard E1921-97 for reactor pressure vessel steels
20. Ic database
21. Basis for revision 2 of the US nuclear regulatory commission's regulatory guide 1.99
22. Evaluation of variability in material properties and chemical composition for midland reactor weld WF-70
23. On the utilization of high-rate pre-cracked Charpy test results and the Master Curve to obtain accurate lower bound toughness predictions in the ductile-to-brittle transition
24. Effect of loading rate on fracture toughness of pressure vessel steels
25. Research results supporting enhanced fracture analysis methods for nuclear reactor pressure vessels
26. An overview of FAVOR: A fracture analysis computer code for nuclear reactor pressure vessels
27. IA
28. Empirical validation of the Master Curve for irradiated and unirradiated reactor pressure vessel steels
29. Size scaling of toughness in the transition: A single variable experiment and data base assessment
30. Cleavage fracture in surface cracked plates: Experiments and numerical predictions