The ASME code cases N-629 and N-631 permit the use of a master curve-based index temperature (RTToT0+19.4°C) as an alternative to traditional RTNDT-based methods of positioning the ASME KIC and KIR curves. This approach was adopted to enable the use of master curve technology without requiring the wholesale changes to the structure of the ASME code that would be needed to use all aspects of master curve technology. For the brittle failure analysis considering irradiation embrittlement an additional procedure to predict the adjustment of fracture toughness for end of life (EOL) from irradiation surveillance results must be available as by NRC R.G. 1.99 Rev. 2, e.g., the adjusted reference temperature is defined as ART=initialRTNDT+ΔRTNDT+margin. The conservatism of this procedure when RTNDT is replaced by RTTo is investigated for western nuclear grade pressure vessel steels and their welds. Based on a systematic evaluation of nearly 100 different irradiated material data sets, a simple relation between RTToirr, RTToref, and ΔT41JRG is proposed. The relation makes use of the R.G. 1.99 Rev. 2 and enables the minimizing of margins, necessary for conventional correlations based on temperature shifts. As an example, the method is used to assess the RTTo as a function of fluence for several German pressure vessel steels and corresponding welds. It is shown that the method is robust and well suited for codification.

1.
Marston
,
T. U.
, ed., 1978, “
Flaw Evaluation Procedures—Background and Application of ASME Section XI Appendix A
,” Report No. EPRI NP-719-SR,
Electric Power Research Institute
, Palo Alto, CA.
2.
Server
,
L. W.
,
Rosinski
,
S. T.
,
Hoffman
,
C.
,
Byrne
,
S.
,
Yoon
,
K.
, and
Lott
,
R.
, 1998, “
Application of Master Curve Fracture Toughness Methodology for Ferritic Steels
,” EPRI Technical Report No. TR-108390, EPRI, Palo Alto, CA.
3.
Wallin
,
K.
, 1999, “
Statistical Re-evaluation of the ASME KIC and KIR Fracture Toughness Reference Curves
,”
Nucl. Eng. Des.
0029-5493,
193
, pp.
317
326
.
4.
Kirk
,
M.
, and
Mitchell
,
M.
, 2000, “
A Review of Technical and Regulatory Developments Needed to Enable Application of Master Curve Technology to the Fracture Integrity Assessment of Commercial Nuclear Power Reactors
,”
Applications of Fracture Mechanics in Failure Assessment
, PVP Vol.
412
,
ASME
, New York.
5.
Keim
,
E.
,
Siegele
,
D.
, and
Nagel
,
G.
, 2005, “
Validation of RTTo for German Reactor Pressure Vessel Steels
,”
Proceedings 2005 ASME Pressure Vessels and Piping Division Conference
, Denver, CO, July 17–21, Paper No. PVP2005-71197.
6.
Sokolov
,
M.
, and
Nanstad
,
R. K.
, 1999, “
Comparison of Irradiation-Induced Shifts of KJC and Charpy Impact Toughness for Reactor Pressure Vessel Steels: Effects of Radiation on Materials
,”
Proceedings 18th International Symposium, ASTM STP 1325
,
R. K.
Nanstad
,
M. L.
Hamilton
,
F. A.
Garner
, and
A. S.
Kumar
, eds.,
American Society for Testing and Materials
,
West Conshohocken, PA
, ASTM, pp.
167
190
.
7.
Wallin
,
K.
, 2004, “
Determination of Correlation Between T41J and T0
,” VTT Paper No. BTUO72-041289.
8.
U.S Nuclear Regulatory Commission
, 1988, “
Radiation Embrittlement of Reactor Vessel Materials
,”
Regulatory Guide 1.99 Revision 2
, Washington, DC.
9.
Nanstad
,
R. K.
,
Haggag
,
F. M.
,
McCabe
,
D. E.
,
Iskander
,
S. K.
,
Bowman
,
K. O.
, and
Menke
,
B. H.
, 1992, “
Irradiation Effects on Fracture Toughness of Two High-Copper Submerged-Arc Welds
,”
HSSI series 5
, Paper No. NUREG∕CR-5913.
10.
ASME Code Sec XI, IWB 3500 Acceptance Standards.
11.
Wallin
,
K.
, 1997, “
Re-evaluation of Thermal Shock Experiment Results Based on the VTT Approach for Statistical Treatment of Fracture Toughness Data
,”
Nucl. Eng. Des.
0029-5493,
174
, pp.
205
218
.
12.
Wallin
,
K.
, 2002, “
Master Curve Analysis of the “Euro” Fracture Toughness Dataset
,”
Eng. Fract. Mech.
0013-7944,
69
, pp.
451
481
.
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